WorldWideScience

Sample records for bioresearch monitoring inspections

  1. Doping, the Inspection Game, and Bayesian Monitoring

    OpenAIRE

    Roland Kirstein

    2009-01-01

    Doping tests create a signal of whether the athlete has acted fraudulently. If the signal is costly, but perfect, then the doping enforcer and the athlete play an “inspection game," which has no equilibrium in pure strategies. This paper presents a modification of that game: The “Bayesian monitoring" model rests on the assumption that signals are available without cost, but vulnerable to two types of errors. Both the inspection game and the new model assume that the enforcer is interested in ...

  2. Automatic mobile inspecting and monitoring device

    International Nuclear Information System (INIS)

    Purpose: To eliminate a treating operation of a signal transmission cable for an automatic mobile inspecting and monitoring device. Constitution: Signals from respective pieces monitoring equipment carried on a monitoring vehicle are temporarily stored in a memory by the operation of an arithmetic controller. When the vehicle reaches each repeating station, the stored contents of the memory are sequentially read by an instruction from the controller, and are applied through a connector to the repeating station. The station is connected through a connecting cable penetrating a reactor container to an operation and monitor board. Thus a long cable for connecting the vehicle to the penetration is unnecessary, thereby eliminating the signal transmission cable treating operation. (Yoshino, Y.)

  3. Inspection systems for valves monitoring at EDF

    International Nuclear Information System (INIS)

    Electricite de France (EDF) makes increasing use of valve inspection systems to guarantee safety in its pressurized water reactor plants, improve plant availability and facilitate condition-based maintenance. A portable system known as SAMIR has been developed for inspection of motor-operated valves, and is now used on EDF's 900-MW sites. For its 1300-MW units, EDF has chosen a more complete system which enables measuring thrust on the valve stem during a maneuver, using a sensor mounted on the yoke. To detect internal vale leaks, an on-site assessment has demonstrated the economic benefits of acoustic emission techniques. EDF has equipped its sites with analog leak detection systems which may soon be replaced by a digital model now being developed. (authors)

  4. Monitoring system of ECCS injection system upon periodical inspection

    International Nuclear Information System (INIS)

    An ECCS reactor injection system is automatically monitored upon periodical inspection. That is, a memory device stores information of the stand-by state of the ECCS reactor injection system upon periodical inspection. A data input means inputs monitoring item data in the present state. A required monitoring target is designated by the input means. A judging means compares the data of the monitoring target with the stand-by state information successively, to judge whether or not the monitoring target is in a predetermined stand-by state. A display means displays the result of the judgment. In the present system thus constituted, since it can be automatically judged whether or not the ECCS reactor injection system, as a monitoring target, is in the predetermined stand-by state, it is possible to reduce the operator's burden and improve the safety. (I.S.)

  5. 50 CFR 37.42 - Inspection and monitoring.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false Inspection and monitoring. 37.42 Section 37.42 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE, DEPARTMENT OF THE INTERIOR (CONTINUED) THE NATIONAL WILDLIFE REFUGE SYSTEM GEOLOGICAL AND GEOPHYSICAL EXPLORATION OF THE COASTAL PLAIN, ARCTIC NATIONAL WILDLIFE REFUGE,...

  6. Current deflection NDE for pipeline inspection and monitoring

    Science.gov (United States)

    Jarvis, Rollo; Cawley, Peter; Nagy, Peter B.

    2016-02-01

    Failure of oil and gas pipelines can often be catastrophic, therefore routine inspection for time dependent degradation is essential. In-line inspection is the most common method used; however, this requires the insertion and retrieval of an inspection tool that is propelled by the fluid in the pipe and risks becoming stuck, so alternative methods must often be employed. This work investigates the applicability of a non-destructive evaluation technique for both the detection and growth monitoring of defects, particularly corrosion under insulation. This relies on injecting an electric current along the pipe and indirectly measuring the deflection of current around defects from perturbations in the orthogonal components of the induced magnetic flux density. An array of three orthogonally oriented anisotropic magnetoresistive sensors has been used to measure the magnetic flux density surrounding a 6'' schedule-40 steel pipe carrying 2 A quasi-DC axial current. A finite element model has been developed that predicts the perturbations in magnetic flux density caused by current deflection which has been validated by experimental results. Measurements of the magnetic flux density at 50 mm lift-off from the pipe surface are stable and repeatable to the order of 100 pT which suggests that defect detection or monitoring growth of corrosion-type defects may be possible with a feasible magnitude of injected current. Magnetic signals are additionally incurred by changes in the wall thickness of the pipe due to manufacturing tolerances, and material property variations. If a monitoring scheme using baseline subtraction is employed then the sensitivity to defects can be improved while avoiding false calls.

  7. Development of the module inspection system for new standardized radiation monitoring modules

    International Nuclear Information System (INIS)

    This report mentions about the module inspection system which does the maintenance check of the monitoring modules adapted the new monitoring standard, as well as the result of the verification of the modules. The module inspection system is the automatic measurement system with the computer. The system can perform the functional and the characteristic examination of the monitoring modules, the calibration with radiation source and inspection report. In the verification of the monitoring module, three major items were tested, the adaptability for the new monitoring standard, the module functions and each characteristics. All items met the new monitoring standard. (author)

  8. Monitoring System for the Inspection of Vehicle Loads for Radioactivity

    International Nuclear Information System (INIS)

    From the nuclear facilities, inactive scrap may have to be sent periodically for disposal. The scrap is to be monitored to ensure that it is free from inadvertent mix up of contaminated material, which has got the potential of unwanted exposure to people as well as costly and time consuming clean up operations. Earlier the scrap carrying vehicles were monitored manually using portable radiation survey monitors by health physicists. A PC based monitoring system for the inspection of vehicle loads for radioactivity is developed and is in use which requires minimum manual interaction. The advantage of the system is that it can automatically screen all outgoing vehicles from the establishment. The PC based system consists of two detector boxes, each having three Plastic Scintillation detectors of 50 mm dia x 500 mm long. The processing unit is built around a PC addon card. Using the calibration factor (i.e., nGy/h per cps), the dose rate is computed and 'allow' / 'disallow' visual signal is generated in the PC located in a control room. The graphical user interface provides ON / OFF button for controlling the counting process and counting time interval can be set by the user as desired. All the six counters are synchronized for the process of counting. The acquired counts are displayed on the PC screen in the form of a count rate vs. time graph. At the completion of scanning of a vehicle, the counting is continued to acquire background radiation level till the next vehicle arrives. The processing unit estimates the radiation dose rate from these recorded counts by using already established calibration factor and displays the data on the monitor screen of the computer. If the determined dose rate exceeds the pre determined limit, an audio alarm is initiated and the alarm information is displayed on the monitor of the computer. The system has provision to enter information like vehicle registration number, type of the vehicle, origin of the load, destination etc. These

  9. Monitoring well inspection and maintenance plan Y-12 Plant, Oak Ridge, Tennessee (revised)

    International Nuclear Information System (INIS)

    Inspection and maintenance of groundwater monitoring wells is a primary element of the Oak Ridge Y-12 Plant Groundwater Protection Program (GWPP). This document is the revised groundwater monitoring well inspection and maintenance plan for the U.S. Department of Energy (DOE) Y-12 Plant in Oak Ridge, Tennessee. The plan provides a systematic program for: (1) inspecting the physical condition of monitoring wells at the Y-12 Plant and (2) identifying maintenance needs that will extend the life of each well and ensure that representative groundwater quality samples and hydrologic data are collected from the wells. Original documentation for the Y-12 Plant GWPP monitoring well inspection and maintenance program was provided in HSW, Inc. 1991a. The original revision of the plan specified that only a Monitoring Well Inspection/Maintenance Summary need be updated and reissued each year. Rapid growth of the monitoring well network and changing regulatory requirements have resulted in constant changes to the status of wells (active or inactive) listed on the Monitoring Well Inspection/Maintenance Summary. As a result, a new mechanism to track the status of monitoring wells has been developed and the plan revised to formalize the new business practices. These changes are detailed in Sections 2.4 and 2.5

  10. Y-12 Groundwater Protection Program Monitoring Well Inspection and Maintenance Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    This document is the fourth revision of the Monitoring Well Inspection and Maintenance Plan for groundwater monitoring wells installed at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee. This plan describes the systematic approach for: inspecting the physical condition of monitoring wells at Y-12, determining maintenance needs that extend the life of a well, and identifying those wells that no longer meet acceptable monitoring well design or well construction standards and require plugging and abandonment. This plan applies to groundwater monitoring wells installed at Y-12 and the related waste management facilities located within the three hydrogeologic regimes.

  11. Y-12 Groundwater Protection Program Monitoring Well Inspection And Maintenance Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    This document is the fourth revision of the Monitoring Well Inspection and Maintenance Plan for groundwater monitoring wells installed at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee. This plan describes the systematic approach for:  inspecting the physical condition of monitoring wells at Y-12,  determining maintenance needs that extend the life of a well, and  identifying those wells that no longer meet acceptable monitoring well design or well construction standards and require plugging and abandonment.

  12. Qualitative health monitoring and incipient damage inspection/evaluation

    OpenAIRE

    Ayres, John W.

    1996-01-01

    Real-time structural integrity monitoring is a concept that is becoming a reality in the engineering community. It will soon be possible for a structure to warn the user when its own structural integrity has been altered. A qualitative impedance-based health monitoring technique, which can be implemented for real-time damage evaluation of complex structures, is investigated. The basic principle of the technique is to monitor the structure's mechanical impedance which will ...

  13. Enhanced defect of interest [DOI] monitoring by utilizing sensitive inspection and ADRTrue SEM review

    Science.gov (United States)

    Kirsch, Remo; Zeiske, Ulrich; Shabtay, Saar; Beyer, Mirko; Yerushalmi, Liran; Goshen, Oren

    2011-03-01

    As semiconductor process design rules continue to shrink, the ability of optical inspection tools to separate between true defects and nuisance becomes more and more difficult. Therefore, monitoring Defect of Interest (DOI) become a real challenge (Figure 1). This phenomenon occurs due to the lower signal received from real defects while noise levels remain almost the same, resulting in inspection high nuisance rate, which jeopardizes the ability to provide a meaningful, true defect Pareto. A non-representative defect Pareto creates a real challenge to a reliable process monitoring (Figure 4). Traditionally, inspection tool recipes were optimized to keep data load at a manageable level and provide defect maps with ~10% nuisance rate, but as defects of interest get smaller with design rule shrinkage, this requirement results in a painful compromise in detection sensitivity. The inspection is usually followed by defect review and classification using scanning electron microscope (SEM), the classification done manually and it is performed on a small sample of the inspection defect map due to time and manual resources limitations. Sample is usually 50~60 randomly selected locations, review is performed manually most of the times, and manual classification is performed for all the reviewed locations. In the approach described in this paper, the inspection tool recipe is optimized for sensitivity rather than low nuisance rate (i.e. detect all DOI with compromising on a higher nuisance rate). Inspection results with high nuisance rate introduce new challenges for SEM review methodology & tools. This paper describe a new approach which enhances process monitoring quality and the results of collaborative work of the Process Diagnostic & Control Business Unit of Applied Materials® and GLOBALFOUNDRIES® utilizing Applied Materials ADRTrueTM & SEMVisionTM capabilities. The study shows that the new approach reveals new defect types in the Pareto, and improves the ability to

  14. Optimization of monitoring and inspections in the life-cycle of wind turbines

    Science.gov (United States)

    Hanish Nithin, Anu; Omenzetter, Piotr

    2016-04-01

    The past decade has witnessed a surge in the offshore wind farm developments across the world. Although this form of cleaner and greener energy is beneficial and eco-friendly, the production of wind energy entails high life-cycle costs. The costs associated with inspections, monitoring and repairs of wind turbines are primary contributors to the high costs of electricity produced in this way and are disadvantageous in today's competitive economic environment. There is limited research being done in the probabilistic optimization of life-cycle costs of offshore wind turbines structures and their components. This paper proposes a framework for assessing the life cycle cost of wind turbine structures subject to damage and deterioration. The objective of the paper is to develop a mathematical probabilistic cost assessment framework which considers deterioration, inspection, monitoring, repair and maintenance models and their uncertainties. The uncertainties are etched in the accuracy and precision of the monitoring and inspection methods and can be considered through the probability of damage detection of each method. Schedules for inspection, monitoring and repair actions are demonstrated using a decision tree. Examples of a generalised deterioration process integrated with the cost analysis using a decision tree are shown for a wind turbine foundation structure.

  15. Capacity building improve Malaysia's inspection and monitoring system for aquaculture and fishery products

    NARCIS (Netherlands)

    Gevers, G.J.M.; Zoontjes, P.W.; Essers, M.L.; Klijnstra, M.; Gerssen, A.

    2012-01-01

    The project aimed to help build a credible inspection and monitoring system that can guarantee safe quality products of Ministry of Health (MoH) and Department of Fisheries (DoF) by upgrading the analytical capacity of the laboratory staff directly involved in the analysis and detection of forbidden

  16. Distributed Monitoring and Control System of Bearing Test and Inspection Center

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    Distributed bearing test center monitoring and controlsystem based on CAN bus is designed in this paper. It canmonitor bearing test process, collect test data, analyze vibrationsignals, extract features of bearing failure and diagnose bearingfaults. The system has been used in a bearing test and inspec-tion center of a bearing plant successfully.

  17. Y-12 Groundwater Protection Program Monitoring Well Inspection and Maintenance Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2006-12-01

    This document is the third revision of the 'Monitoring Well Inspection and Maintenance Plan' for groundwater wells associated with the US Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee. This plan describes the systematic approach for: (1) inspecting the physical condition of monitoring wells at Y-12; (2) identifying maintenance needs that extend the life of the well and assure well-head protection is in place, and (3) identifying wells that no longer meet acceptable monitoring-well design or well construction standards and require plugging and abandonment. The inspection and maintenance of groundwater monitoring wells is one of the primary management strategies of the Y-12 Groundwater Protection Program (GWPP) Management Plan, 'proactive stewardship of the extensive monitoring well network at Y-12' (BWXT 2004a). Effective stewardship, and a program of routine inspections of the physical condition of each monitoring well, ensures that representative water-quality monitoring and hydrologic data are able to be obtained from the well network. In accordance with the Y-12 GWPP Monitoring Optimization Plan (MOP) for Groundwater Monitoring Wells at the Y-12 National Security Complex, Oak Ridge, Tennessee (BWXT 2006b), the status designation (active or inactive) for each well determines the scope and extent of well inspections and maintenance activities. This plan, in conjunction with the above document, formalizes the GWPP approach to focus available resources on monitoring wells which provide the most useful data. This plan applies to groundwater monitoring wells associated with Y-12 and related waste management facilities located within the three hydrogeologic regimes: (1) the Bear Creek Hydrogeologic Regime (Bear Creek Regime); (2) the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime); and (3) the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek Regime encompasses a section of the

  18. Results of calendar year 1994 monitor well inspection and maintenance program, Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This document is a compendium of results of the calendar year 1994 Monitor Well Inspection and Maintenance Program at the Department of Energy Y-12 Plant in Oak Ridge, Tennessee. This report documents the work relating to well inspections and maintenance requests. Inspections are implemented in order to better assess the condition and maintenance needs of wells that are actively being monitored. Currently this approach calls for inspecting all wells on a routine (annual or triennial) basis which are: (1) in an active sampling program; (2) included in a hydrologic study; or (3) not in service, but not scheduled for plugging and abandonment. Routine inspections help to ensure that representative groundwater samples and hydrologic data are being collected, and contribute to the life expectancy of each well. This report formally presents well inspection and maintenance activities that were conducted at the Y-12 Plant during 1994. All inspections were conducted between April and December

  19. Results of calendar year 1994 monitor well inspection and maintenance program, Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    McMaster, B.W. [Univ. of Tennessee, Knoxville, TN (United States); Jones, S.B.; Sitzler, J.L. [Oak Ridge National Lab., TN (United States)

    1995-06-01

    This document is a compendium of results of the calendar year 1994 Monitor Well Inspection and Maintenance Program at the Department of Energy Y-12 Plant in Oak Ridge, Tennessee. This report documents the work relating to well inspections and maintenance requests. Inspections are implemented in order to better assess the condition and maintenance needs of wells that are actively being monitored. Currently this approach calls for inspecting all wells on a routine (annual or triennial) basis which are: (1) in an active sampling program; (2) included in a hydrologic study; or (3) not in service, but not scheduled for plugging and abandonment. Routine inspections help to ensure that representative groundwater samples and hydrologic data are being collected, and contribute to the life expectancy of each well. This report formally presents well inspection and maintenance activities that were conducted at the Y-12 Plant during 1994. All inspections were conducted between April and December.

  20. A multi-criteria decision model to determine inspection intervals of condition monitoring based on delay time analysis

    International Nuclear Information System (INIS)

    In periodic monitoring, the main problem is determining the inspection interval of condition monitoring. For this problem, the decision variable is represented by the time of next inspection of condition monitoring. There are several studies that deal with prescribing inspection intervals. But only a few of these allow the decision maker to observe simultaneously more than one aspect. This does not accord with the natural tendency of the decision maker who desires to see the decision problem from a broader perspective, by having different viewpoints or dimensions of choices. Therefore, the main objective of this paper is to propose a decision model, which can simultaneously determine inspection intervals for condition monitoring regarding the failure behavior of equipment to be inspected, features of maintainability and decision maker preferences about cost and downtime

  1. Intelligent mobile sensor system for drum inspection and monitoring: Phase 1

    International Nuclear Information System (INIS)

    The objective of this project was to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The device is capable of operating in narrow aisles and interpolating the free aisle space between rows of stacked drums. The system has an integrated sensor suite for leak detection, and is interfaced with a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which positions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 90% of all drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase one is now complete. The first phase has demonstrated an integrated system for monitoring and inspection activities for waste storage facility operations. This demonstration system was quickly fielded and evaluated by leveraging technologies developed from previous NASA and DARPA contracts and internal research. The second phase will demonstrate a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project

  2. Corrosion and erosion monitoring in plates and pipes using constant group velocity Lamb wave inspection.

    Science.gov (United States)

    Nagy, Peter B; Simonetti, Francesco; Instanes, Geir

    2014-09-01

    Recent improvements in tomographic reconstruction techniques generated a renewed interest in short-range ultrasonic guided wave inspection for real-time monitoring of internal corrosion and erosion in pipes and other plate-like structures. Emerging evidence suggests that in most cases the fundamental asymmetric A0 mode holds a distinct advantage over the earlier market leader fundamental symmetric S0 mode. Most existing A0 mode inspections operate at relatively low inspection frequencies where the mode is highly dispersive therefore very sensitive to variations in wall thickness. This paper examines the potential advantages of increasing the inspection frequency to the so-called constant group velocity (CGV) point where the group velocity remains essentially constant over a wide range of wall thickness variation, but the phase velocity is still dispersive enough to allow accurate wall thickness assessment from phase angle measurements. This paper shows that in the CGV region the crucial issue of temperature correction becomes especially simple, which is particularly beneficial when higher-order helical modes are also exploited for tomography. One disadvantage of working at such relatively high inspection frequency is that, as the slower A0 mode becomes faster and less dispersive, the competing faster S0 mode becomes slower and more dispersive. At higher inspection frequencies these modes cannot be separated any longer based on their vibration polarization only, which is mostly tangential for the S0 mode while mostly normal for the A0 at low frequencies, as the two modes become more similar as the frequency increases. Therefore, we propose a novel method for suppressing the unwanted S0 mode based on the Poisson effect of the material by optimizing the angle of inclination of the equivalent transduction force of the Electromagnetic Acoustic Transducers (EMATs) used for generation and detection purposes. PMID:24582555

  3. Efficient management of inspection and monitoring data for a better maintenance of infrastructure

    International Nuclear Information System (INIS)

    In North America, Europe and Japan, government agencies and large private owners are now facing the challenge of maintaining, with limited resources, large stocks of vital structures like traditional and nuclear power plants, Cooling towers but also highways, railways, bridges, dams, harbors, industrial facilities etc. These structures are representing a large amount of money, have not been designed to be easily repaired or replaced, and are getting older and more vulnerable. People involved in structure management have developed extensive technical methods and tools to monitor the condition of the structure and establish the diagnosis. Each authority has been developing is own inspection maintenance procedures, taking into account their specificity, their different priorities, safety requirements, resources and range of competence. In most cases visual inspections are used to detect deteriorations, to rank structures, define priorities, estimate repair costs, etc. These visual inspections require to record, report, analyze and store for years large quantities of data (inspection records, drawings, photos) and it is easy to get lost in the clerical work. Moreover a number of decision steps (inspection record, ranking of defects, long-term analysis) are still highly subjective and can greatly affect the quality of the final diagnosis. An inspection-based management software system has been developed to optimize this process and provide decision-makers with objective information on the condition of the infrastructure. The system is a comprehensive management system which integrates: database of structural defects, on-site computerized record, analysis, maintenance, diagnosis, repair and budgetary functionalities. This paper describes the basic functions and benefits of the system. (authors)

  4. Concept for in-service inspections and operational monitoring of components belonging to Swiss safety categories 1 to 4

    International Nuclear Information System (INIS)

    The present paper shows a concept for in-service inspections and operational monitoring of components belonging to safety categories 1 to 4. Furthermore, requirements on testing methods and in-service inspections of engineered safeguards against excess pressure are discussed. (RW)

  5. Gas centrifuge enrichment plants inspection frequency and remote monitoring issues for advanced safeguards implementation

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian David [Los Alamos National Laboratory; Erpenbeck, Heather H [Los Alamos National Laboratory; Miller, Karen A [Los Alamos National Laboratory; Ianakiev, Kiril D [Los Alamos National Laboratory; Reimold, Benjamin A [Los Alamos National Laboratory; Ward, Steven L [Los Alamos National Laboratory; Howell, John [GLASGOW UNIV.

    2010-09-13

    Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to verify declared low enriched uranium (LEU) production, detect undeclared LEU production and detect high enriched uranium (BEU) production with adequate probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of declared cylinders of uranium hexafluoride that are used in the process of enrichment at GCEPs. This paper contains an analysis of how possible improvements in unattended and attended NDA systems including process monitoring and possible on-site destructive analysis (DA) of samples could reduce the uncertainty of the inspector's measurements providing more effective and efficient IAEA GCEPs safeguards. We have also studied a few advanced safeguards systems that could be assembled for unattended operation and the level of performance needed from these systems to provide more effective safeguards. The analysis also considers how short notice random inspections, unannounced inspections (UIs), and the concept of information-driven inspections can affect probability of detection of the diversion of nuclear material when coupled to new GCEPs safeguards regimes augmented with unattended systems. We also explore the effects of system failures and operator tampering on meeting safeguards goals for quantity and timeliness and the measures needed to recover from such failures and anomalies.

  6. 2011 Groundwater Monitoring and Inspection Report Gnome-Coach Site, New Mexico

    International Nuclear Information System (INIS)

    Gnome-Coach was the site of a 3-kiloton underground nuclear test in 1961. Surface and subsurface contamination resulted from the underground nuclear testing, post-test drilling, and groundwater tracer test performed at the site. The State of New Mexico is currently proceeding with a conditional certificate of completion for the surface. As for the subsurface, monitoring activities that include hydraulic head monitoring and groundwater sampling of the wells onsite are conducted as part of the annual site inspection. These activities were conducted on January 19, 2011. The site roads, monitoring well heads, and the monument at surface ground zero were observed as being in good condition at the time of the site inspection. An evaluation of the hydraulic head data obtained from the site indicates that water levels in wells USGS-4 and USGS-8 appear to respond to the on/off cycling of the dedicated pump in well USGS-1 and that water levels in wells LRL-7 and DD-1 increased during this annual monitoring period. Analytical results obtained from the sampling indicate that concentrations of tritium, strontium-90, and cesium-137 were consistent with concentrations from historical sampling events.

  7. 2011 Groundwater Monitoring and Inspection Report Gnome-Coach Site, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    None

    2012-02-01

    Gnome-Coach was the site of a 3-kiloton underground nuclear test in 1961. Surface and subsurface contamination resulted from the underground nuclear testing, post-test drilling, and groundwater tracer test performed at the site. The State of New Mexico is currently proceeding with a conditional certificate of completion for the surface. As for the subsurface, monitoring activities that include hydraulic head monitoring and groundwater sampling of the wells onsite are conducted as part of the annual site inspection. These activities were conducted on January 19, 2011. The site roads, monitoring well heads, and the monument at surface ground zero were observed as being in good condition at the time of the site inspection. An evaluation of the hydraulic head data obtained from the site indicates that water levels in wells USGS-4 and USGS-8 appear to respond to the on/off cycling of the dedicated pump in well USGS-1 and that water levels in wells LRL-7 and DD-1 increased during this annual monitoring period. Analytical results obtained from the sampling indicate that concentrations of tritium, strontium-90, and cesium-137 were consistent with concentrations from historical sampling events.

  8. Reliability-Based Design and Planning of Inspection and Monitoring of Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Marquez-Dominguez, Sergio

    and offshore wind turbine foundations with the aim of improving the design, decreasing structural costs and increasing benefits. Recently, wind energy technology has started to adopt risk and reliability based inspection planning (RBI) as a methodology based on Bayesian decision theories together......Maintaining and developing a sustainable wind industry is the main motivation of this PhD thesis entitled “Reliability-based design and planning of inspection and monitoring of offshore wind turbines”. In this thesis, statistical methods and probability theory are important mathematical tools used...... produced by the natural phenomena, i.e. wind and waves. This load interaction has an important influence on the dynamical behaviour as well as on the fatigue damage of the wind turbine structure, influencing its reliability and stability. In summation, wind, currents and sea loads can be considered...

  9. A recursive Bayesian framework for structural health management using online monitoring and periodic inspections

    International Nuclear Information System (INIS)

    The necessary information for developing a structural health diagnostic and prognostic solution is often obtained from various sources. This paper presents a Bayesian framework for online integration of the structural health assessment information obtained from empirical crack growth models, structural health monitoring and periodic inspections. The data used in Bayesian updating could be direct damage observations (e.g., observed crack sizes) and/or damage growth rate estimates (e.g., crack growth rate observations). An AE-based monitoring approach is used to obtain the crack growth rate observations in this paper. The outcome of this approach is updated crack size distribution as well as updated parameters for an empirical crack growth model. The model with updated parameters is used for prognosis given an assumed future usage profile

  10. 2015 Groundwater Monitoring and Inspection Report Gnome-Coach, New Mexico, Site

    Energy Technology Data Exchange (ETDEWEB)

    Findlay, Rick [Navarro Research and Engineering, Oak Ridge, TN (United States)

    2016-01-01

    The Gnome-Coach, New Mexico, Site was the location of a 3-kiloton-yield underground nuclear test in 1961 and a groundwater tracer test in 1963. The U.S. Geological Survey conducted the groundwater tracer test using four dissolved radionuclides-tritium, iodine-131, strontium-90, and cesium-137-as tracers. Site reclamation and remediation began after the underground testing and was conducted in several phases at the site. The New Mexico Environment Department (NMED) issued a Conditional Certificate of Completion in September 2014, which documents that surface remediation activities have been successfully completed in accordance with the Voluntary Remediation Program. Subsurface activities have included annual sampling and monitoring of wells at and near the site since 1972. These annual monitoring activities were enhanced in 2008 to include monitoring hydraulic head and collecting samples from the onsite wells USGS-4, USGS-8, and LRL-7 using the low-flow sampling method. In 2010, the annual monitoring was focused to the monitoring wells within the site boundary. A site inspection and annual sampling were conducted on January 27-28, 2015. A second site visit was conducted on April21, 2015, to install warning/notification signs to fulfill a requirement of the Conditional Certificate of Completion that was issued by the NMED for the surface.

  11. Monitoring and inspection techniques for long term storage of higher activity waste packages

    International Nuclear Information System (INIS)

    In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

  12. On-line monitoring and inservice inspection in codes; Betriebsueberwachung und wiederkehrende Pruefungen in den Regelwerken

    Energy Technology Data Exchange (ETDEWEB)

    Bartonicek, J.; Zaiss, W. [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H.R. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany). Geschaeftsstelle des Kerntechnischen Ausschusses (KTA)

    1999-08-01

    The relevant regulatory codes determine the ISI tasks and the time intervals for recurrent components testing for evaluation of operation-induced damaging or ageing in order to ensure component integrity on the basis of the last available quality data. In-service quality monitoring is carried out through on-line monitoring and recurrent testing. The requirements defined by the engineering codes elaborated by various institutions are comparable, with the KTA nuclear engineering and safety codes being the most complete provisions for quality evaluation and assurance after different, defined service periods. German conventional codes for assuring component integrity provide exclusively for recurrent inspection regimes (mainly pressure tests and optical testing). The requirements defined in the KTA codes however always demanded more specific inspections relying on recurrent testing as well as on-line monitoring. Foreign codes for ensuring component integrity concentrate on NDE tasks at regular time intervals, with time intervals scope of testing activities being defined on the basis of the ASME code, section XI. (orig./CB) [Deutsch] Fuer die Komponentenintegritaet sind die Schaedigungsmechanismen mit dem nach den Regelwerken einzuhaltenden Abstand abzusichern. Dabei ist die jeweils vorhandene (Ist-) Qualitaet als Ausgangspunkt entscheidend. Die Absicherung der vorhandenen Qualitaet im weiteren Betrieb erfolgt durch geeignete Betriebsueberwachung und wiederkehrende Pruefungen. Die Anforderungen der Regelwerke sind vergleichbar, wobei die Bestimmung der vorhandenen Qualitaet nach einer bestimmten Betriebszeit sowie deren Absicherung im weiteren Betrieb am vollstaendigsten auf Basis des KTA-Regelwerkes moeglich ist. Die Absicherung der Komponentenintegritaet im Betrieb beruht in deutschen konventionellen Regelwerken nur auf den wiederkehrenden Pruefungen (hauptsaechlich Druckpruefungen und Sichtpruefungen). Das KTA-Regelwerk forderte hier schon immer qualifizierte

  13. 2012 Groundwater Monitoring and Inspection Report Gnome-Coach, New Mexico, Site

    International Nuclear Information System (INIS)

    Gnome-Coach was the site of a 3-kiloton underground nuclear test conducted in 1961. Surface and subsurface contamination resulted from the underground nuclear testing, post-test drilling, and a groundwater tracer test performed at the site. Surface reclamation and remediation began after the underground testing. A Completion Report was prepared, and the State of New Mexico is currently proceeding with a conditional certificate of completion for the surface. Subsurface corrective action activities began in 1972 and have generally consisted of annual sampling and monitoring of wells near the site. In 2008, the annual site inspections were refined to include hydraulic head monitoring and collection of samples from groundwater monitoring wells onsite using the low-flow sampling method. These activities were conducted during this monitoring period on January 18, 2012. Analytical results from this sampling event indicate that concentrations of tritium, strontium-90, and cesium-137 were generally consistent with concentrations from historical sampling events. The exceptions are the decreases in concentrations of strontium-90 in samples from wells USGS-4 and USGS-8, which were more than 2.5 times lower than last year's results. Well USGS-1 provides water for livestock belonging to area ranchers, and a dedicated submersible pump cycles on and off to maintain a constant volume in a nearby water tank. Water levels in wells USGS-4 and USGS-8 respond to the on/off cycling of the water supply pumping from well USGS-1. Well LRL-7 was not sampled in January, and water levels were still increasing when the transducer data were downloaded in September. A seismic reflection survey was also conducted this year. The survey acquired approximately 13.9 miles of seismic reflection data along 7 profiles on and near the site. These activities were conducted from February 23 through March 10, 2012. The site roads, monitoring well heads, and the monument at surface ground zero were in good

  14. 2012 Groundwater Monitoring and Inspection Report Gnome-Coach, New Mexico, Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-03-01

    Gnome-Coach was the site of a 3-kiloton underground nuclear test conducted in 1961. Surface and subsurface contamination resulted from the underground nuclear testing, post-test drilling, and a groundwater tracer test performed at the site. Surface reclamation and remediation began after the underground testing. A Completion Report was prepared, and the State of New Mexico is currently proceeding with a conditional certificate of completion for the surface. Subsurface corrective action activities began in 1972 and have generally consisted of annual sampling and monitoring of wells near the site. In 2008, the annual site inspections were refined to include hydraulic head monitoring and collection of samples from groundwater monitoring wells onsite using the low-flow sampling method. These activities were conducted during this monitoring period on January 18, 2012. Analytical results from this sampling event indicate that concentrations of tritium, strontium-90, and cesium-137 were generally consistent with concentrations from historical sampling events. The exceptions are the decreases in concentrations of strontium-90 in samples from wells USGS-4 and USGS-8, which were more than 2.5 times lower than last year's results. Well USGS-1 provides water for livestock belonging to area ranchers, and a dedicated submersible pump cycles on and off to maintain a constant volume in a nearby water tank. Water levels in wells USGS-4 and USGS-8 respond to the on/off cycling of the water supply pumping from well USGS-1. Well LRL-7 was not sampled in January, and water levels were still increasing when the transducer data were downloaded in September. A seismic reflection survey was also conducted this year. The survey acquired approximately 13.9 miles of seismic reflection data along 7 profiles on and near the site. These activities were conducted from February 23 through March 10, 2012. The site roads, monitoring well heads, and the monument at surface ground zero were in

  15. Inspection systems for valves monitoring at EDF; Systemes d`inspection utilises par EDF pour la surveillance de la robinetterie

    Energy Technology Data Exchange (ETDEWEB)

    Germain, J.L.; Granal, L.; Provost, D.; Touillez, M. [EDF, 75 - Paris (France)]|[Electricite de France (EDF), 78 - Chatou (France)

    1997-10-01

    Electricite de France (EDF) makes increasing use of valve inspection systems to guarantee safety in its pressurized water reactor plants, improve plant availability and facilitate condition-based maintenance. A portable system known as SAMIR has been developed for inspection of motor-operated valves, and is now used on EDF`s 900-MW sites. For its 1300-MW units, EDF has chosen a more complete system which enables measuring thrust on the valve stem during a maneuver, using a sensor mounted on the yoke. To detect internal vale leaks, an on-site assessment has demonstrated the economic benefits of acoustic emission techniques. EDF has equipped its sites with analog leak detection systems which may soon be replaced by a digital model now being developed. (authors).

  16. Post-Closure Inspection and Monitoring Report for the Salmon, Mississippi, Site Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    None

    2008-05-01

    This report summarizes inspection and monitoring activities performed on and near the Salmon, Mississippi, Site in calendar year 2007. The Draft Long-Term Surveillance and Maintenance Plan for the Salmon Site, Lamar County, Mississippi (DOE 2007) specifies the submittal of an annual report of site activities and the results of sample analyses. This report is submitted to comply with that requirement. The Tatum Salt Dome was used by the U.S. Atomic Energy Commission (AEC) for underground nuclear testing during the cold war. The land surface above the salt dome, the Salmon Site, is located in Lamar County, Mississippi, approximately 12 miles west of Purvis (Figure 1). The U.S. Department of Energy (DOE), the successor to the AEC, is responsible for long-term surveillance and maintenance of the site. The DOE Office of Legacy Management (LM) was assigned this responsibility effective October 2006.

  17. Immersion and dry lithography monitoring for flash memories (after develop inspection and photo cell monitor) using a darkfield imaging inspector with advanced binning technology

    Science.gov (United States)

    Parisi, P.; Mani, A.; Perry-Sullivan, C.; Kopp, J.; Simpson, G.; Renis, M.; Padovani, M.; Severgnini, C.; Piacentini, P.; Piazza, P.; Beccalli, A.

    2009-12-01

    After-develop inspection (ADI) and photo-cell monitoring (PM) are part of a comprehensive lithography process monitoring strategy. Capturing defects of interest (DOI) in the lithography cell rather than at later process steps shortens the cycle time and allows for wafer re-work, reducing overall cost and improving yield. Low contrast DOI and multiple noise sources make litho inspection challenging. Broadband brightfield inspectors provide the highest sensitivity to litho DOI and are traditionally used for ADI and PM. However, a darkfield imaging inspector has shown sufficient sensitivity to litho DOI, providing a high-throughput option for litho defect monitoring. On the darkfield imaging inspector, a very high sensitivity inspection is used in conjunction with advanced defect binning to detect pattern issues and other DOI and minimize nuisance defects. For ADI, this darkfield inspection methodology enables the separation and tracking of 'color variation' defects that correlate directly to CD variations allowing a high-sampling monitor for focus excursions, thereby reducing scanner re-qualification time. For PM, the darkfield imaging inspector provides sensitivity to critical immersion litho defects at a lower cost-of-ownership. This paper describes litho monitoring methodologies developed and implemented for flash devices for 65nm production and 45nm development using the darkfield imaging inspector.

  18. Innovative Ultrasonic Techniques for Inspection and Monitoring of Large Concrete Structures

    Directory of Open Access Journals (Sweden)

    Niederleithinger E.

    2013-07-01

    Full Text Available Ultrasonic echo and transmission techniques are used in civil engineering on a regular basis. New sensors and data processing techniques have lead to many new applications in the structural investigation as well as quality control. But concrete structures in the nuclear sector have special features and parameters, which pose problems for the methods and instrumentation currently available, e.g. extreme thickness, dense reinforcement, steel liners or special materials. Several innovative ultrasonic techniques have been developed to deal with these issues at least partly in lab experiments and pilot studies. Modern imaging techniques as multi-offset SAFT have been used e. g. to map delaminations. Thick concrete walls have successfully been inspected, partly through a steel liner. Embedded ultrasonic sensors have been designed which will be used in monitoring networks of large concrete structures above and below ground. In addition, sensitive mathematical methods as coda wave interferometry have been successfully evaluated to detect subtle changes in material properties. Examples of measurements and data evaluation are presented.

  19. Innovative Ultrasonic Techniques for Inspection and Monitoring of Large Concrete Structures

    Science.gov (United States)

    Wiggenhauser, H.; Niederleithinger, E.

    2013-07-01

    Ultrasonic echo and transmission techniques are used in civil engineering on a regular basis. New sensors and data processing techniques have lead to many new applications in the structural investigation as well as quality control. But concrete structures in the nuclear sector have special features and parameters, which pose problems for the methods and instrumentation currently available, e.g. extreme thickness, dense reinforcement, steel liners or special materials. Several innovative ultrasonic techniques have been developed to deal with these issues at least partly in lab experiments and pilot studies. Modern imaging techniques as multi-offset SAFT have been used e. g. to map delaminations. Thick concrete walls have successfully been inspected, partly through a steel liner. Embedded ultrasonic sensors have been designed which will be used in monitoring networks of large concrete structures above and below ground. In addition, sensitive mathematical methods as coda wave interferometry have been successfully evaluated to detect subtle changes in material properties. Examples of measurements and data evaluation are presented.

  20. A magnetostatic force inspection method for monitoring the oscillation marks of continuous casting

    International Nuclear Information System (INIS)

    Based on the well-known fact that ferromagnetic materials can be significantly attracted by a permanent magnet (PM), we develop an innovative magnetostatic force inspection method to monitor the oscillating marks formed during continuous casting. A small PM produces a static magnetic field that penetrates into the ferromagnetic material slab formed via continuous casting. This magnet forms a localized magnetic sensing zone (MSZ) within the ferromagnetic material. The magnetostatic force acting on the ferromagnetic material can be expressed as the Maxwell tensor integral over the surface of the ferromagnetic material within the MSZ. This force provides local surface profile information. The reaction force of the magnetostatic force acting on the PM can be measured using a laser–cantilever system (a high force resolution method), and thus the profile features of the oscillation marks can be obtained. A measuring device with a laser–cantilever system is designed, constructed, and applied in a series of prototypes and a static experiment. A numerical model is simultaneously constructed to validate the measurement results. The differences between the actual and measured profiles are analyzed. An actual steel specimen with oscillation marks is measured using this device, and the accuracy is evaluated. In summary, the potential for the application of this method in the metallurgy industry is demonstrated. (paper)

  1. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Bechtel Nevada

    2006-08-01

    This Post-Closure Inspection and Monitoring Report provides the results and inspections and monitoring for Corrective Action Unit 110: Area 3 Waste Management Division U-3ax/bl Crater, Nevada Test Site, Nevada. This report includes an analysis and summary of the site inpsections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at Corrective Action Unit 110, for the annual period July 2005 thrugh June 2006.

  2. Intelligent Mobile Sensor System for drum inspection and monitoring - Volume 1. Final report, October 1, 1993 - April 22, 1995

    International Nuclear Information System (INIS)

    The objective of the Intelligent Mobile Sensor System (IMSS) project is to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The device is capable of operating in the narrow free aisle space between rows of stacked drums. The system has an integrated sensor suite for problem-drum detection, and is linked to a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase two is now complete. The first phase demonstrated an integrated system (maturity level IVa) for monitoring and inspection activities for waste storage facility operations. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project. This report summarizes the design and evaluation of the new IMSS Phase 2 system and vehicle

  3. Intelligent Mobile Sensor System for drum inspection and monitoring -- Volume 1. Final report, October 1, 1993--April 22, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The objective of the Intelligent Mobile Sensor System (IMSS) project is to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The device is capable of operating in the narrow free aisle space between rows of stacked drums. The system has an integrated sensor suite for problem-drum detection, and is linked to a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase two is now complete. The first phase demonstrated an integrated system (maturity level IVa) for monitoring and inspection activities for waste storage facility operations. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project. This report summarizes the design and evaluation of the new IMSS Phase 2 system and vehicle.

  4. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-03-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

  5. Intelligent mobile sensor system for drum inspection and monitoring: Phase 1. Topical report, October 1, 1992--June 8, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    The objective of this project was to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The device is capable of operating in narrow aisles and interpolating the free aisle space between rows of stacked drums. The system has an integrated sensor suite for leak detection, and is interfaced with a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which positions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 90% of all drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase one is now complete. The first phase has demonstrated an integrated system for monitoring and inspection activities for waste storage facility operations. This demonstration system was quickly fielded and evaluated by leveraging technologies developed from previous NASA and DARPA contracts and internal research. The second phase will demonstrate a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project.

  6. Sensor-based monitoring and inspection of surface morphology in ultraprecision manufacturing processes

    Science.gov (United States)

    Rao, Prahalad Krishna

    This research proposes approaches for monitoring and inspection of surface morphology with respect to two ultraprecision/nanomanufacturing processes, namely, ultraprecision machining (UPM) and chemical mechanical planarization (CMP). The methods illustrated in this dissertation are motivated from the compelling need for in situ process monitoring in nanomanufacturing and invoke concepts from diverse scientific backgrounds, such as artificial neural networks, Bayesian learning, and algebraic graph theory. From an engineering perspective, this work has the following contributions: 1. A combined neural network and Bayesian learning approach for early detection of UPM process anomalies by integrating data from multiple heterogeneous in situ sensors (force, vibration, and acoustic emission) is developed. The approach captures process drifts in UPM of aluminum 6061 discs within 15 milliseconds of their inception and is therefore valuable for minimizing yield losses. 2. CMP process dynamics are mathematically represented using a deterministic multi-scale hierarchical nonlinear differential equation model. This process-machine inter-action (PMI) model is evocative of the various physio-mechanical aspects in CMP and closely emulates experimentally acquired vibration signal patterns, including complex nonlinear dynamics manifest in the process. By combining the PMI model predictions with features gathered from wirelessly acquired CMP vibration signal patterns, CMP process anomalies, such as pad wear, and drifts in polishing were identified in their nascent stage with high fidelity (R2 ~ 75%). 3. An algebraic graph theoretic approach for quantifying nano-surface morphology from optical micrograph images is developed. The approach enables a parsimonious representation of the topological relationships between heterogeneous nano-surface fea-tures, which are enshrined in graph theoretic entities, namely, the similarity, degree, and Laplacian matrices. Topological invariant

  7. Specialists' meeting on in-service inspection and monitoring of LMFBRs. Summary report

    International Nuclear Information System (INIS)

    The purpose of the meeting sponsored by the IAEA on the recommendation of the International Working Group on Fast Reactors (IWGFR) was attended by participants from France, the Federal Republic of Germany, Italy, Japan, the Netherlands, United Kingdom, United States of America, and two international organizations: CEC and IAEA. The purpose of the meeting was to review and discuss inspection requirements and concepts developed in the IWGFR member countries, development of inspection methods and their application in practical work and to recommend future development. The technical sessions were divided into four topical sessions as follows: General Concepts for In-Service Inspection of the Reactor Plant; Remotely Controlled Inspection Systems; Ultrasonic Test Methods; Miscellaneous Test Methods

  8. Multi-Path Guided Wave Imaging for Inspection and Monitoring of Large, Complex Structures Project

    Data.gov (United States)

    National Aeronautics and Space Administration — There is a well-recognized need within NASA and the aerospace community at large for rapid and reliable methods for inspection of large, complex structures. This...

  9. A study of the long-range inspection method for on-line monitoring of pipes in nuclear power plants

    International Nuclear Information System (INIS)

    Deployment of an advanced on-line monitoring of the component integrity offers the prospect of an improved performance, enhanced safety, and reduced overall cost for nuclear power plants (NPPs). Also ultrasonic guided ultrasonic wave has been known as one of the promising techniques that could be utilized for on-line monitoring, because it enables us to undertake a long-range inspection of structures such as plates and pipes. The present work is aimed at developing a new method using ultrasonic guided waves for the on-line monitoring of pipes. For this purpose we fabricated the necessary hardware and carried out transmitter tuning, group velocity measurement, receiver tuning, and mode identification. Finally we carried out an experiment on a long-range inspection with the developed hardware and the techniques. In the experiment, we could detect the flaws at a distance of about 20M from the transmitter, and we could verify the possibility of using the developed hardware and techniques for on-line monitoring of pipes in NPPs

  10. Intelligent Mobile Sensor System for drum inspection and monitoring - Volume 2. Final report, October 1, 1993 - April 22, 1995

    International Nuclear Information System (INIS)

    The objective of the Intelligent Mobile Sensor System (IMSS) project was to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort was a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The system has an integrated sensor suite for problem-drum detection, and creates and maintains a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort was separated into three phases of which phase three is now complete. The first phase demonstrated an integrated system (maturity level IVa) for monitoring and inspection activities for waste storage facility operations. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype employed an integrated design that considered operational requirements, hardware costs, maintenance, safety, and robustness. The final phase has demonstrated the commercial viability of the vehicle in operating waste storage facilities at Fernald, Ohio and the Idaho National Engineering Laboratory (INEL). This report summarizes the system upgrades performed in phase 3 and the evaluation of the IMSS Phase 3 system and vehicle

  11. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-11-01

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

  12. Intelligent Mobile Sensor System for drum inspection and monitoring -- Volume 2. Final report, October 1, 1993--April 22, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The objective of the Intelligent Mobile Sensor System (IMSS) project was to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort was a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The system has an integrated sensor suite for problem-drum detection, and creates and maintains a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort was separated into three phases of which phase three is now complete. The first phase demonstrated an integrated system (maturity level IVa) for monitoring and inspection activities for waste storage facility operations. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype employed an integrated design that considered operational requirements, hardware costs, maintenance, safety, and robustness. The final phase has demonstrated the commercial viability of the vehicle in operating waste storage facilities at Fernald, Ohio and the Idaho National Engineering Laboratory (INEL). This report summarizes the system upgrades performed in phase 3 and the evaluation of the IMSS Phase 3 system and vehicle.

  13. 2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

    International Nuclear Information System (INIS)

    This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

  14. Intelligent mobile sensor system for drum inspection and monitoring: Topical report, October 1, 1993--April 22, 1995

    International Nuclear Information System (INIS)

    The objective of the Intelligent Mobile Sensor System (IMSS) project is to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The system has an integrated sensor suite for problem-drum detection, and is linked to a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase two is now complete. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project. This report summarizes the design and evaluation of the new IMSS Phase 2 system and vehicle. Several parts of the IMSS Phase 1 Topical (Final) Report, which describes the requirements, design guidelines, and detailed design of the Phase 1 IMSS vehicle, are incorporated here, with modifications to reflect the changes in the design and the new elements added during the Phase 2 work

  15. Intelligent mobile sensor system for drum inspection and monitoring: Topical report, October 1, 1993--April 22, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    The objective of the Intelligent Mobile Sensor System (IMSS) project is to develop an operational system for monitoring and inspection activities for waste storage facility operations at several DOE sites. Specifically, the product of this effort is a robotic device with enhanced intelligence and maneuverability capable of conducting routine inspection of stored waste drums. The system has an integrated sensor suite for problem-drum detection, and is linked to a site database both for inspection planning and for data correlation, updating, and report generation. The system is capable of departing on an assigned mission, collecting required data, recording which portions of its mission had to be aborted or modified due to environmental constraints, and reporting back when the mission is complete. Successful identification of more than 96% of drum defects has been demonstrated in a high fidelity waste storage facility mockup. Identified anomalies included rust spots, rust streaks, areas of corrosion, dents, and tilted drums. All drums were positively identified and correlated with the site database. This development effort is separated into three phases of which phase two is now complete. The second phase demonstrated a prototype system appropriate for operational use in an actual storage facility. The prototype provides an integrated design that considers operational requirements, hardware costs, maintenance, safety, and robustness. The final phase will demonstrate commercial viability using the prototype vehicle in a pilot waste operations and inspection project. This report summarizes the design and evaluation of the new IMSS Phase 2 system and vehicle. Several parts of the IMSS Phase 1 Topical (Final) Report, which describes the requirements, design guidelines, and detailed design of the Phase 1 IMSS vehicle, are incorporated here, with modifications to reflect the changes in the design and the new elements added during the Phase 2 work.

  16. Vision-Inspection System for Residue Monitoring of Ready-Mixed Concrete Trucks

    Directory of Open Access Journals (Sweden)

    Deok-Seok Seo

    2015-01-01

    Full Text Available The objective of this study is to propose a vision-inspection system that improves the quality management for ready-mixed concrete (RMC. The proposed system can serve as an alternative to the current visual inspection method for the detection of residues in agitator drum of RMC truck. To propose the system, concept development and the system-level design should be executed. The design considerations of the system are derived from the hardware properties of RMC truck and the conditions of RMC factory, and then 6 major components of the system are selected in the stage of system level design. The prototype of system was applied to a real RMC plant and tested for verification of its utility and efficiency. It is expected that the proposed system can be employed as a practical means to increase the efficiency of quality management for RMC.

  17. Reliability-based design and planning of inspection and monitoring of offshore wind turbines

    DEFF Research Database (Denmark)

    Dominguez, Sergio Marquez

    When the wind is blowing fiercely, wind turbines must resist. Wind turbines have to withstand the rough environmental conditions in the most reliable manner and start to produce renewable energy when the wind becomes friendly again. Never give up ‘wind turbine’ face the winds and be proud of...... contributing as an energy sources. Reading this thesis, the reader will get the basic knowledge necessary for successful application of the main theories of structural reliability applied to both onshore and offshore wind turbine substructures considering building materials as steel and concrete. Additionally...... probability and statistics for application in structural reliability-based risk inspections....

  18. 2010 Groundwater Monitoring and Inspection Report Gnome-Coach Site, New Mexico

    International Nuclear Information System (INIS)

    This report presents the 2010 groundwater monitoring results collected by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) at the Gnome-Coach (Gnome) Site in New Mexico (Figure 1). Groundwater monitoring consisted of collecting hydraulic head data and groundwater samples from the wells on site. Historically, the U.S. Environmental Protection Agency (EPA) had conducted these annual activities under the Long-Term Hydrologic Monitoring Program (LTHMP). LM took over the sampling and data collection activities in 2008 but continues to use the EPA Radiation and Indoor Environments National Laboratory in Las Vegas, Nevada, to analyze the water samples. This report summarizes groundwater monitoring and site investigation activities that were conducted at the site during calendar year 2010.

  19. 2010 Groundwater Monitoring and Inspection Report Gnome-Coach Site, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-02-01

    This report presents the 2010 groundwater monitoring results collected by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) at the Gnome-Coach (Gnome) Site in New Mexico (Figure 1). Groundwater monitoring consisted of collecting hydraulic head data and groundwater samples from the wells on site. Historically, the U.S. Environmental Protection Agency (EPA) had conducted these annual activities under the Long-Term Hydrologic Monitoring Program (LTHMP). LM took over the sampling and data collection activities in 2008 but continues to use the EPA Radiation and Indoor Environments National Laboratory in Las Vegas, Nevada, to analyze the water samples. This report summarizes groundwater monitoring and site investigation activities that were conducted at the site during calendar year 2010.

  20. Development and Testing of an Acoustoultrasonic Inspection Device for Condition Monitoring of Wind Turbine Blades

    DEFF Research Database (Denmark)

    McGugan, Malcolm

    2011-01-01

    In recent years the wind energy industry has grown rapidly (23% per annum) to the stage where a modern turbine blade exceeds the wing span of an Airbus A380, where offshore wind farms of 300MW are a reality, and where an 800MW total level of European power production 15 years ago has become a...... significant 10,000MW in 2010, with this rate of growth forecast to continue despite a general economic slowdown. One of the many challenges this industry has (and continues) to face concerns the polymer fiber composite material and structure utilized in the wind turbine blades. This large, complex, multi......-layered structure must meet the requirements of greater size and quality demanded by the industry, whilst matching the harsher environments of offshore placement, and providing improvements in reliability and an upgraded life-cycle maintenance approach. Non-destructive inspection technology is an important topic...

  1. Inspection of copper canisters for spent nuclear fuel by means of ultrasound. Ultrasonic imaging, FSW monitoring with acoustic emission

    Energy Technology Data Exchange (ETDEWEB)

    Stepinski, Tadeusz (ed.); Olofsson, Tomas; Wennerstroem, Erik [Uppsala Univ., Dept. of Technical Sciences (Sweden). Signals and Systems

    2006-12-15

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in years 2005/2006. In the first part of the report we propose a concept of monitoring of the friction stir welding (FSW) process by means of acoustic emission (AE) technique. First, we introduce the AE technique and then we present the principle of the system for monitoring the FSW process in cylindrical symmetry specific for the SKB canisters. We propose an omnidirectional circular array of ultrasonic transducers for receiving the AE signals generated by the FSW tool and the releases of the residual stress at canister's circumference. Finally, we review the theory of uniform circular arrays. The second part of the report is concerned with synthetic aperture focusing technique (SAFT) characterized by enhanced spatial resolution. We evaluate three different approaches to perform imaging with less computational cost than that of the extended SAFT (ESAFT) method proposed in our previous reports. First, a sparse version of ESAFT is presented, which solves the reconstruction problem only for a small set of the most probable scatterers in the image. A frequency domain the {omega}-k SAFT algorithm, which relies on the far-field approximation is presented in the second part. Finally, a detailed analysis of the most computationally intense step in the ESAFT and the sparse 2D deconvolution is presented. In the final part of the report we introduce basics of the 3D ultrasonic imaging that has a great potential in the inspection of the FSW welds. We discuss in some detail the three interrelated steps involved in the 3D ultrasonic imaging: data acquisition, 3D reconstruction, and 3D visualization.

  2. Inspection of copper canisters for spent nuclear fuel by means of ultrasound. Ultrasonic imaging, FSW monitoring with acoustic emission

    International Nuclear Information System (INIS)

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in years 2005/2006. In the first part of the report we propose a concept of monitoring of the friction stir welding (FSW) process by means of acoustic emission (AE) technique. First, we introduce the AE technique and then we present the principle of the system for monitoring the FSW process in cylindrical symmetry specific for the SKB canisters. We propose an omnidirectional circular array of ultrasonic transducers for receiving the AE signals generated by the FSW tool and the releases of the residual stress at canister's circumference. Finally, we review the theory of uniform circular arrays. The second part of the report is concerned with synthetic aperture focusing technique (SAFT) characterized by enhanced spatial resolution. We evaluate three different approaches to perform imaging with less computational cost than that of the extended SAFT (ESAFT) method proposed in our previous reports. First, a sparse version of ESAFT is presented, which solves the reconstruction problem only for a small set of the most probable scatterers in the image. A frequency domain the ω-k SAFT algorithm, which relies on the far-field approximation is presented in the second part. Finally, a detailed analysis of the most computationally intense step in the ESAFT and the sparse 2D deconvolution is presented. In the final part of the report we introduce basics of the 3D ultrasonic imaging that has a great potential in the inspection of the FSW welds. We discuss in some detail the three interrelated steps involved in the 3D ultrasonic imaging: data acquisition, 3D reconstruction, and 3D visualization

  3. Bioresearch Monitonoring Information System (BMIS)

    Data.gov (United States)

    U.S. Department of Health & Human Services — The publication Approved Drug Products with Therapeutic Equivalence Evaluations (the List, commonly known as the Orange Book) identifies drug products approved on...

  4. The Use of Explosion Aftershock Probabilities for Planning and Deployment of Seismic Aftershock Monitoring System for an On-site Inspection

    Science.gov (United States)

    Labak, P.; Ford, S. R.; Sweeney, J. J.; Smith, A. T.; Spivak, A.

    2011-12-01

    One of four elements of CTBT verification regime is On-site inspection (OSI). Since the sole purpose of an OSI shall be to clarify whether a nuclear weapon test explosion or any other nuclear explosion has been carried out, inspection activities can be conducted and techniques used in order to collect facts to support findings provided in inspection reports. Passive seismological monitoring, realized by the seismic aftershock monitoring (SAMS) is one of the treaty allowed techniques during an OSI. Effective planning and deployment of SAMS during the early stages of an OSI is required due to the nature of possible events recorded and due to the treaty related constrains on size of inspection area, size of inspection team and length of an inspection. A method, which may help in planning the SAMS deployment is presented. An estimate of aftershock activity due to a theoretical underground nuclear explosion is produced using a simple aftershock rate model (Ford and Walter, 2010). The model is developed with data from the Nevada Test Site and Semipalatinsk Test Site, which we take to represent soft- and hard-rock testing environments, respectively. Estimates of expected magnitude and number of aftershocks are calculated using the models for different testing and inspection scenarios. These estimates can help to plan the SAMS deployment for an OSI by giving a probabilistic assessment of potential aftershocks in the Inspection Area (IA). The aftershock assessment combined with an estimate of the background seismicity in the IA and an empirically-derived map of threshold magnitude for the SAMS network could aid the OSI team in reporting. We tested the hard-rock model to a scenario similar to the 2008 Integrated Field Exercise 2008 deployment in Kazakhstan and produce an estimate of possible recorded aftershock activity.

  5. Infrared thermography inspection and monitoring in oil and gas and petrochemical plant industry

    International Nuclear Information System (INIS)

    Infrared thermography is an electronic technique that quite literally allows us to see thermal energy. The technique allows for the monitoring of temperatures and thermal patterns while the equipment is online and running under full load. Armed with guidelines of allowable operating temperature limits of the equipment, the technique may enhances company's, ?ability to predict equipment failure and plan corrective action before a costly shutdown, equipment damage, or personal injury occurs. Infrared thermography is an excellent condition monitoring tool to assist in the reduction of maintenance costs on mechanical, electrical and equipment. With this new capability plant maintenance personnel have recognized infrared thermography as one of the most versatile and effective condition monitoring tools available today. Infrared can be used on a wide variety of equipment including pumps, motors, bearings, pulleys, fans, drives, conveyors etc. This paper will explain the benefits of Infrared Thermography as a condition monitoring tool for plant equipment and mechanical systems and some examples of infrared thermography application is discussed. (Author)

  6. Monitoring pipeline movement and its effect on pipe integrity using inertial/caliper in-line inspection

    Energy Technology Data Exchange (ETDEWEB)

    Czyz, Jaroslaw A. [BJ Pipeline Inspection Services, Calgary (Canada); Wainselboin, Sergio E. [BJ Services do Brasil Ltda., Macae, RJ (Brazil)

    2003-07-01

    Pipeline movement is caused by a variety of sources, such as landslides, earthquakes, overburden, field subsidence, permafrost thaw or heave, riverbed erosion, seabed scouring, fishing trawlers, ship anchors, construction in the pipeline right of way, temperature and pressure increase or cycles. It poses a threat to pipeline integrity as it can lead to excessive strain in the pipe, pipeline buckling, as well as development of severe pipe wall deformations. For the above reasons it is important to monitor both the pipeline movement and the deformations caused by it. This can be accurately and efficiently achieved by performing in-line inspections with the Geopig{sup R}. The inertial navigation system on board the tool allows for accurate 3-D measurements of the pipe centerline position and curvature that is used for calculation of the bending strain and provides high accuracy pipeline geometry data for FEM modelling and analysis. Comparison of two surveys at different times is used for precise monitoring of the pipeline movement and bending strain changes between the runs. The Geopig also records caliper measurements of the pipe wall shape, which allows for detection of wrinkles and other pipe anomalies that develop as the result of the pipeline displacement. This paper demonstrates the advantages of inertial/caliper survey for monitoring and prevention of pipeline movement for a variety of applications. It presents examples of detected wrinkles, buckles and large strains induced by pipeline movement that required mitigation to avert pipeline failure. It shows a history of monitoring pipeline strain, movement and wall deformations over years. (author)

  7. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada, for Calendar Year 2007

    International Nuclear Information System (INIS)

    This report presents data collected during the annual post-closure site inspection conducted at the Central Nevada Test Area Surface Corrective Action Unit (CAU) 417 in May 2007. The annual post-closure site inspection included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspection conducted at the UC-1 Central Mud Pit (CMP) indicated the site and soil cover were in good condition. No new cracks or fractures were observed in the soil cover during the annual inspection. A crack on the west portion of the cover was observed during the last quarterly inspection in December 2006. This crack was filled with bentonite as part of the maintenance activities conducted in February 2007 and will be monitored during subsequent annual inspections. The vegetation on the soil cover was adequate but showing signs of the area's ongoing drought. No issues were identified with the CMP fence, gate, or subsidence monuments. New DOE Office of Legacy Management signs with updated emergency phone numbers were installed as part of this annual inspection, no issues were identified with the warning signs and monuments at the other two UC-1 locations. The annual subsidence survey was conducted at UC-1 CMP and UC-4 Mud Pit C as part of the maintenance activities conducted in February 2007. The results of the subsidence surveys indicate that the covers are performing as expected, and no unusual subsidence was observed. A vegetation survey of the UC-1 CMP cover and adjacent areas was conducted as part of the annual inspection in May 2007. The vegetation survey indicated that revegetation continues to be successful, although stressed due to the area's prevailing drought conditions. The vegetation should continue to be monitored to document any changes in the plant community and to identify conditions that could potentially require remedial action to maintain a viable vegetation

  8. US monitoring and verification technology: on-site inspection experience and future challenges

    International Nuclear Information System (INIS)

    The United States has a long and successful history of cooperation with treaty partners in monitoring and verification. For strategic arms reduction treaties, our collaboration has resulted in the development and application of systems with limited complexity and intrusiveness. As we progress beyond New START (NST) along the 'road to zero', the reduced number of nuclear weapons is likely to require increased confidence in monitoring and verification techniques. This may place increased demands on the technology to verify the presence of a nuclear weapon and even confirm the presence of a certain type. Simultaneously, this technology must include the ability to protect each treaty partner's sensitive nuclear weapons information. Mutual development of this technology by treaty partners offers the best approach for acceptance in treaty negotiations. This same approach of mutual cooperation and development is essential for developing nuclear test monitoring technology in support of the Comprehensive Nuclear Test Ban Treaty (CTBT). Our ability to detect low yield and evasive testing will be enhanced through mutually developed techniques and experiments using laboratory laser experiments and high explosives tests in a variety of locations and geologies. (authors)

  9. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-03-01

    This report presents results of data collected during the annual post-closure site inspections conducted at the Central Nevada Test Area surface Corrective Action Unit (CAU) 417 in May 2011 and July 2012. The annual post-closure site inspections included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspections conducted at the UC-1 Central Mud Pit (CMP) indicated that the site and soil cover were in good condition. No new fractures or extension of existing fractures were observed and no issues with the fence or gate were identified. The vegetation on the cover continues to look healthy, but the biennial vegetation survey conducted during the 2012 inspection indicated that the total foliar cover was slightly higher in 2009 than in 2012. This may be indicative of a decrease in precipitation observed during the 2-year monitoring period. The precipitation totaled 9.9 inches from July 1, 2010, through June 30, 2011, and 5 inches from July 1, 2011, through June 30, 2012. This decrease in precipitation is also evident in the soil moisture data obtained from the time domain reflectometry sensors. Soil moisture content data show that the UC-1 cover is performing as designed, and evapotranspiration is effectively removing water from the cover.

  10. Optimal Inspection Policy for Three-state Systems Monitored by Variable Sample Size Control Charts

    OpenAIRE

    Wu, Shaomin

    2011-01-01

    This paper presents the expected long-run cost per unit time for a system monitored by an adaptive control chart with variable sample sizes: if the control chart signals that the system is out of control, the sampling which follows will be conducted with a larger sample size. The system is supposed to have three states: in-control, out-of-control, and failed. Two levels of repair are applied to maintain the system. A minor repair will be conducted if an assignable cause is c...

  11. Monitoring inspection for radiocesium in agricultural, livestock, forestry and fishery products in Fukushima prefecture

    International Nuclear Information System (INIS)

    We selected and re-categorized the monitoring data opened by the government of Fukushima prefecture focusing on the radiocesium concentrations in four agricultural products, from the data on 90,000 samples analyzed during 3 years. Radioactivity was found to be high during 3 months after the accident because of direct fallout. The internal exposure in the area with the highest contamination area of rice during the first 3 months was calculated and estimated to be 0.75 mSv year-1. The radioactivity in foods products rapidly decreased after 3 months later, but in the case of some forestry products and fish, there are still some products in which radioactivity was above the regulated value, 100 Bq kg-1. (author)

  12. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 342: Area 23 Mercury Fire Training Pit, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    This report provides a summary and analysis of visual site inspections and soil gas sampling results for Corrective Action Unit (CAU) 342, Area 23 Mercury Fire Training Pit. CAU 342 is identified in the Federal Facility Agreement and Consent Order of 1996 and consists of Corrective Action Site 23-56-01, Former Mercury Fire Training Pit. This report covers calendar years 2004 and 2005. Visual site inspections were conducted on May 20 and November 14, 2004, and May 17 and November 15, 2005. No significant findings were observed during these inspections. The site was in good condition, and no repair activities were required. Soil gas samples were collected on November 29, 2005, for analysis of volatile organic compounds (VOCs) and semivolatile organic compounds (SVOCs), and samples were collected on December 1, 2005, for analysis of base gases. Base gas concentrations in the monitoring well show a high concentration of carbon dioxide and a low concentration of oxygen, which is an indication of biodegradation of total petroleum hydrocarbons (TPH) in the soil. Results for VOCs and SVOCs are unchanged, with VOCs below or near laboratory method detection limits and no SVOCs detected above laboratory method detection limits. Post-closure monitoring was required for six years after closure of the site. Therefore, since 2005 was the sixth year of monitoring, the effectiveness of natural attenuation of the TPH-impacted soil by biodegradation was evaluated. The base gas concentrations indicate that biodegradation of TPH in the soil is occurring; therefore, it is recommended that monitoring be discontinued. Visual site inspections should continue to be performed biannually to ensure that the signs are in place and readable and that the use restriction has been maintained. The results of the site inspections will be documented in a letter report and submitted annually

  13. Devices of new generation for the anti-terrorist inspection and on-boundary customs radiation monitoring

    International Nuclear Information System (INIS)

    ; - the heavy oxide scintillators of the type GSO, BGO and etc. substantially exceed alkali-halide scintillators both according to the loading characteristics (dynamic range) and on the radiation-thermal durability; - SCS of the type ZnSe(Cd) is one of the best materials for the dosimetry of the super-power mixed radiation fluxes. The realization of project on the creation of the equipment for new generation for the customs- boundary radiation monitoring is intended to carry out together with the 'Institute of Single Crystals', Kharkov, NAS of Ukraine and Azerbaijan National Aerospace Agency, Baku, NAS of Azerbaijan. The 'Institute of Single Crystals' is the leading organization in the Ukraine on obtaining, investigating the properties and application of traditional and new scintillation materials. Azerbaijan National Aerospace Agency NAS of Azerbaijan is the leading organization of Azerbaijan on the creation of the instruments of radiation monitoring. Between the 'Institute of Single Crystals' and ANASA has already been achieved scientifically- consultative collaboration on questions of the optimization of systems for RM. The purpose of project is theoretical substantiation and the practical realization of the highly effective stationary and mobile instruments of new generation for the anti-terrorist inspection and boundary- customs radiation monitoring on the basis of the new types of the detectors, which have high sensitivity α -, β-, γ- and to neutron emission, with the possibility of determining the isotopic composition in the regime of rapid analysis (compact movable spectrometer). Project will have not only the scientific and technical, but also social value, directed toward an improvement in the psychological stability in the society. Equipment for the realization of the project: reactors for the synthesis of raw material for PPS and oxide scintillators; growth furnaces; instruments for the control of output characteristics and studies of the properties of new

  14. Inspection and monitoring plan, contaminated groundwater seeps 317/319/ENE Area, Argonne National Laboratory

    International Nuclear Information System (INIS)

    During the course of completing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) in the 317/319/East-Northeast (ENE) Area of Argonne National Laboratory-East (ANL-E), groundwater was discovered moving to the surface through a series of groundwater seeps. The seeps are located in a ravine approximately 600 ft south of the ANL-E fence line in Waterfall Glen Forest Preserve. Samples of the seep water were collected and analyzed for selected parameters. Two of the five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14--25 microg/L), carbon tetrachloride (56--340 microg/L), and tetrachloroethylene (3--6 microg/L). The other seeps did not contain detectable levels of volatile organics. The nature of the contaminants in the seeps will also be monitored on a regular basis. Samples of surface water flowing through the bottom of the ravine and groundwater emanating from the seeps will be collected and analyzed for chemical and radioactive constituents. The results of the routine sampling will be compared with the concentrations used in the risk assessment. If the concentrations exceed those used in the risk assessment, the risk calculations will be revised by using the higher numbers. This revised analysis will determine if additional actions are warranted

  15. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 417: Central Nevada Test Area Surface, Hot Creek Valley, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    None

    2009-01-01

    This report presents data collected during the annual post-closure site inspection conducted at the Central Nevada Test Area Surface Corrective Action Unit (CAU) 417 in May of 2008. The annual post-closure site inspection included inspections of the UC-1, UC-3, and UC-4 sites in accordance with the Post-Closure Monitoring Plan provided in the CAU 417 Closure Report (NNSA/NV 2001). The annual inspection conducted at the UC-1 Central Mud Pit (CMP) indicated that the site and soil cover were in good condition. Three new cracks or fractures were observed in the soil cover during the annual inspection and were immediately filled with bentonite chips. The vegetation on the soil cover was adequate, but showed signs of the area's ongoing drought. No issues were identified with the CMP fence, gate, or subsidence monuments. No issues were identified with the warning signs and monuments at the other two UC-1 locations. The annual subsidence survey was conducted at UC-1 CMP and UC-4 Mud Pit C in August 2008. The results of the subsidence surveys indicate that the covers are performing as expected, and no unusual subsidence was observed.

  16. POST-CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 112: AREA 23 HAZARDOUS WASTE TRENCHES, NEVADA TEST SITE, NEVADA; FOR THE PERIOD OCTOBER 2003 - SEPTEMBER 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2004-12-01

    Corrective Action Unit (CAU) 112, Area 23 Hazardous Waste Trenches, Nevada Test Site (NTS), Nevada, is a Resource Conservation and Recovery Act (RCRA) unit located in Area 23 of the NTS. This annual Post-Closure Inspection and Monitoring Report provides the results of inspections and monitoring for CAU 112. This report includes a summary and analysis of the site inspections, repair and maintenance, meteorological information, and neutron soil moisture monitoring data obtained at CAU 112 for the current monitoring period, October 2003 through September 2004. Inspections of the CAU 112 RCRA unit were performed quarterly to identify any significant physical changes to the site that could impact the proper operation of the waste unit. The overall condition of the covers and facility was good, and no significant findings were observed. The annual subsidence survey of the elevation markers was conducted on August 23, 2004, and the results indicated that no cover subsidence4 has occurred at any of the markers. The elevations of the markers have been consistent for the past 11 years. The total precipitation for the current reporting period, october 2003 to September 2004, was 14.0 centimeters (cm) (5.5 inches [in]) (National Oceanographic and Atmospheric Administration, Air Resources Laboratory, Special Operations and Research Division, 2004). This is slightly below the average rainfall of 14.7 cm (5.79 in) over the same period from 1972 to 2004. Post-closure monitoring verifies that the CAU 112 trench covers are performing properly and that no water is infiltrating into or out of the waste trenches. Sail moisture measurements are obtained in the soil directly beneath the trenches and compared to baseline conditions for the first year of post-closure monitoring, which began in october 1993. neutron logging was performed twice during this monitoring period along 30 neutron access tubes to obtain soil moisture data and detect any changes that may indicate moisture movement

  17. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2006-08-01

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2005 through June 2006. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and UR warning signs was good. Settling was observed that exceeded the action level as specified in Section VILB.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Along the east edge of the cover (repaired previously in August 2003, December 2003, May 2004, October 2004), an area of settling was observed during the December 2005 inspection to again be above the action level, and required repair. This area and two other areas of settling on the cover that were first observed during the December 2005 inspection were repaired in February 2006. The semiannual subsidence surveys were done in September 2005 and March 2006. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.015 m [-0.05 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring on the cover. Soil moisture results obtained to date indicate that the CAU 110 cover is performing as expected. Time Domain Reflectometry (TDR) data indicated an increase in soil moisture (1

  18. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2005 through June 2006. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and UR warning signs was good. Settling was observed that exceeded the action level as specified in Section VILB.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Along the east edge of the cover (repaired previously in August 2003, December 2003, May 2004, October 2004), an area of settling was observed during the December 2005 inspection to again be above the action level, and required repair. This area and two other areas of settling on the cover that were first observed during the December 2005 inspection were repaired in February 2006. The semiannual subsidence surveys were done in September 2005 and March 2006. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.015 m [-0.05 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring on the cover. Soil moisture results obtained to date indicate that the CAU 110 cover is performing as expected. Time Domain Reflectometry (TDR) data indicated an increase in soil moisture (1

  19. Inspection and market-based regulation through emissions trading. The striking reliance on self-monitoring, self-reporting and verification

    International Nuclear Information System (INIS)

    This contribution discusses inspection with regard to emissions trading. It focuses on the EU greenhouse gas emissions trading scheme. The core rule of emissions trading is that industries need to cover their emissions with tradable emission rights. There are several options for the government to distribute those rights, basically through a free allocation or an auction. The need to cover emissions with a tradable right gives a financial incentive to firms to choose for the reduction of emissions, of course related to the market price of the tradable right. This price-incentive at the same time urges governments to put in place a sound enforcement approach. One of the characteristics of current emissions trading schemes is that they heavily rely on self-monitoring duties. Nevertheless, the ultimate responsibility to inspect rests on the government. However, with the introduction of emissions trading a remarkable shift takes place: instead of the more traditional control of the actual behaviour of industries, inspection by the government ranges under the greenhouse gas emissions-trading instrument much more towards the control of self-monitoring activities. The use of verifiers within the EU greenhouse gas emissions trading scheme is in this respect a unique new provision, but at the same time raises many practical and fundamental questions.

  20. Information-Driven Inspections

    International Nuclear Information System (INIS)

    New uranium enrichment capacity is being built worldwide in response to perceived shortfalls in future supply. To meet increasing safeguards responsibilities with limited resources, the nonproliferation community is exploring next-generation concepts to increase the effectiveness and efficiency of safeguards, such as advanced technologies to enable unattended monitoring of nuclear material. These include attribute measurement technologies, data authentication tools, and transmission and security methods. However, there are several conceptual issues with how such data would be used to improve the ability of a safeguards inspectorate such as the International Atomic Energy Agency (IAEA) to reach better safeguards conclusions regarding the activities of a State. The IAEA is pursuing the implementation of information-driven safeguards, whereby all available sources of information are used to make the application of safeguards more effective and efficient. Data from continuous, unattended monitoring systems can be used to optimize on-site inspection scheduling and activities at declared facilities, resulting in fewer, better inspections. Such information-driven inspections are the logical evolution of inspection planning - making use of all available information to enhance scheduled and randomized inspections. Data collection and analysis approaches for unattended monitoring systems can be designed to protect sensitive information while enabling information-driven inspections. A number of such inspections within a predetermined range could reduce inspection frequency while providing an equal or greater level of deterrence against illicit activity, all while meeting operator and technology holder requirements and reducing inspector and operator burden. Three options for using unattended monitoring data to determine an information-driven inspection schedule are to (1) send all unattended monitoring data off-site, which will require advances in data analysis techniques to

  1. Information-Driven Inspections

    Energy Technology Data Exchange (ETDEWEB)

    Laughter, Mark D [ORNL; Whitaker, J Michael [ORNL; Lockwood, Dunbar [U.S. Department of Energy, NNSA

    2010-01-01

    New uranium enrichment capacity is being built worldwide in response to perceived shortfalls in future supply. To meet increasing safeguards responsibilities with limited resources, the nonproliferation community is exploring next-generation concepts to increase the effectiveness and efficiency of safeguards, such as advanced technologies to enable unattended monitoring of nuclear material. These include attribute measurement technologies, data authentication tools, and transmission and security methods. However, there are several conceptual issues with how such data would be used to improve the ability of a safeguards inspectorate such as the International Atomic Energy Agency (IAEA) to reach better safeguards conclusions regarding the activities of a State. The IAEA is pursuing the implementation of information-driven safeguards, whereby all available sources of information are used to make the application of safeguards more effective and efficient. Data from continuous, unattended monitoring systems can be used to optimize on-site inspection scheduling and activities at declared facilities, resulting in fewer, better inspections. Such information-driven inspections are the logical evolution of inspection planning - making use of all available information to enhance scheduled and randomized inspections. Data collection and analysis approaches for unattended monitoring systems can be designed to protect sensitive information while enabling information-driven inspections. A number of such inspections within a predetermined range could reduce inspection frequency while providing an equal or greater level of deterrence against illicit activity, all while meeting operator and technology holder requirements and reducing inspector and operator burden. Three options for using unattended monitoring data to determine an information-driven inspection schedule are to (1) send all unattended monitoring data off-site, which will require advances in data analysis techniques to

  2. Annual Report RCRA Post-Closure Monitoring and Inspections for Corrective Action Unit 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the Period October 2001 - October 2002

    Energy Technology Data Exchange (ETDEWEB)

    G. Richardson

    2003-02-01

    This annual monitoring and inspection report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Injection Well during the October 2001 to October 2002 period. The U-3fi Injection Well is located in Area 3 of the Nevada Test Site (NTS), Nye County, Nevada. Inspections of the Area 3 U-3fi Injection Well are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste disposal unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 128-meter (m) (420-feet [ft]) ER3-3 monitoring well and detect changes that may be indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft).

  3. Innovative alpha-radioactivity monitor for clearance level inspection based on ionized air transportation technology (1). Comparison with mass spectral analysis using uranium-attached samples

    International Nuclear Information System (INIS)

    We have been developing an alpha-radioactivity monitor based on ionized air transportation technology (alpha clearance monitor) for efficiently performing clearance level inspection of massive amounts of uranium-contaminated waste. This paper is one of a series related to a method for quantitatively evaluating alpha radioactivity from a measured ion current value. Using a prototype alpha clearance monitor, we measured alpha radioactivities of uranium-attached components used in back-end facilities of the nuclear fuel cycle (uranium-attached samples). We compared the measured radioactivities with reference radioactivities by assaying the samples with an inductively coupled plasma mass spectrometer and the radioactivities measured with a scintillation survey meter. The radioactivities of curved plate samples measured with the prototype monitor were highly linear with respect to the reference radioactivities (a residual standard deviation of 8%). Absolute values of the radioactivities obtained with the prototype monitor and with the survey meter were about 40% and 50% smaller than the reference radioactivities, respectively. Measurements of complex-shaped samples indicated that, to measure diverse-shaped waste, it was necessary to classify the waste by shape and determine conversion coefficients corresponding to each group in advance, experimentally and theoretically. (author)

  4. Inspection Database

    Data.gov (United States)

    U.S. Department of Health & Human Services — FDA is disclosing the final inspection classification for inspections related to currently marketed FDA-regulated products. The disclosure of this information is...

  5. Inspection planning

    International Nuclear Information System (INIS)

    Slovenian Nuclear Safety Administration (SNSA) division of nuclear and radiological safety inspection has developed systematic approach to their inspections. To be efficient in their efforts regarding regular and other types of inspections, in past years, the inspection plan has been developed. It is yearly based and organized on a such systematic way, that all areas of nuclear safety important activities of the licensee are covered. The inspection plan assures appropriate preparation for conducting the inspections, allows the overview of the progress regarding the areas to be covered during the year. Depending on the licensee activities and nature of facility (nuclear power plant, research reactor, radioactive waste storage, others), the plan has different levels of intensity of inspections and also their frequency. One of the basic approaches of the plan is to cover all nuclear and radiological important activities on such way, that all regulatory requests are fulfilled. In addition, the inspection plan is a good tool to improve inspection effectiveness based on previous experience and allows to have the oversight of the current status of fulfillment of planned inspections. Future improvement of the plan is necessary in the light of newest achievements on this field in the nuclear world, that means, new types of inspections are planned and will be incorporated into plan in next year.(author)

  6. On-Line Monitoring and Dynamic Feature Trending as a Means to Improve In-Service Inspection, Maintenance, and Long-Term Assessment of Systems and Components

    International Nuclear Information System (INIS)

    The recent publication of an international standard on vibration monitoring of reactor internal structures (IEC 61502, standard of the International Electrotechnical Commission) concludes a long-standing development of methods for a new type of nuclear power plant instrumentation and control system. This new system differs from traditional monitoring systems, as it is aimed primarily at early failure detection. Useful information is provided to plant operators, but in particular to the inspection/maintenance personnel. Powerful modern computer technology allows - in an effective manner - correlation and spectral analysis, feature extraction and trending, alert level monitoring, and remote data/signature transmission of dynamic process signals such as neutron noise, vibration signals, pressure noise, etc. The signature and feature trends are stored in a central databank and form a useful reference for assessment of components and systems in case of actual incipient failure development or at the estimated end of the plant lifetime as part of the aging condition assessment measures.The standard IEC 61502 is used as an example for early failure detection and on-line condition monitoring methods based on signature analysis and feature vector monitoring in general. The reasons/background for structuring this particular standard in a mandatory and an optional part as well as the resulting consequences are explained. But emphasis is also placed on demonstration of the principles, i.e., measurement analysis and usefulness of such methods for maintenance and refurbishment strategies. The transferability of the methods is discussed when applied for other tasks, for instance, for condition/aging assessment of process instrumentation

  7. On-line primary flow monitoring in the PWR hot legs during in-service inspection using high temperature ultrasonic sensors

    International Nuclear Information System (INIS)

    The monitoring of the water level in French PWR hot legs during reactor shut-down for in-service inspection and reloading is of particular importance for safety reasons. At the present time, an ultrasonic probe (commercially available) is installed during this period for such a purpose. Due to the fact that this sensor can not stand high temperature and irradiation conditions in operations, it has to be taken out before restarting the reactor. That is to say that such monitoring has a cost in term of sensor maintenance and in term of integrated doses of the employees. In the frame of the ALARA (As Low As Reasonable Achievable) policy of EDF, our laboratory at CEA-Cadarache, which is in charge of the development of measurement systems for nuclear reactors, has carried-out an important R and D project in order to prove the feasibility of a permanent device which can be installed under the leg and which can support operational conditions of the reactor even in abnormal situations. This device uses High Temperature Ultra-Sonic Transducer which was developed and qualified originally for inspection under sodium in the French Fast Reactors (Superphenix and Phenix). The sensor is based on lithium niobate adapted for nuclear environment (LiNbO3) protected by a stainless steel case and works in the range of 0.7 - 4.5 MHz frequency. At the moment, such sensors are used in an industrial context in Phenix reactor for fuel assembly vibration surveillance. These transducers can support temperature up to 600degC, thermal shocks of 20degC/s and integrated dose up to 3 109 Gy. The R and D project consisted in studying the use of such a sensor for water level monitoring in the hot leg. Transmission of ultrasonic waves through the steel of the pipe, coupling between the sensor and the pipe using non-organic materials, performance evaluation on scale-1 mock-up have been evaluated and give very interesting results. Our paper will present in detail the result of the qualification of the

  8. Incore inspection device

    International Nuclear Information System (INIS)

    The device of the present invention can inspect surfaces of equipments in reactor water in a nuclear reactor in a state of atmospheric air. Namely, an inspection device is movable forwardly and backwardly in a water-proof vessel. An annular sucker with pleats is disposed to the outer side of a lid of the water-proof vessel. A television camera for an under water monitoring is disposed to the inner side of the lid of the water-proof vessel by way of a partitioning wall with lid. Transferring screws are disposed at the back and on the side of the water-proof vessel. In the device having such a constitution, (1) the inside of the water-proof vessel is at first made water-tight by closing the partitioning wall with lid, (2) the back and the side screws are operated by the guide of the underwater monitoring television camera, to transfer the water-proof vessel to the surface of the reactor core to be inspected, (3) the annular sucker with pleats is urged on the surface to be inspected by the back screw, to fix the water-proof vessel, (4) reactor water in a space of the annular sucker with pleats is discharged and replaced with air, and (5) the lid of the partition wall with lid is opened and the inspection device is disposed at a position of the underwater monitoring television camera, to inspect the surface to be inspected in a state of atmospheric air. (I.S.)

  9. Inspection of copper canister for spent nuclear fuel by means of ultrasound. Copper characterization, FSW monitoring with acoustic emission and ultrasonic imaging

    Energy Technology Data Exchange (ETDEWEB)

    Stepinski, Tadeusz (ed.); Engholm, Marcus; Olofsson, Tomas (Uppsala Univ., Signals and Systems, Dept. of Technical Sciences, Uppsala (Sweden))

    2009-08-15

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in 2008. The first part of the report is concerned with aspects related to ultrasonic attenuation of copper material used for canisters. We present results of attenuation measurement performed for a number of samples taken from a real canister; two from the lid and four from different parts of canister wall. Ultrasonic attenuation of the material originating from canister lid is relatively low (less that 50 dB/m) and essentially frequency independent in the frequency range up to 5 MHz. However, for the material originating from the extruded canister part considerable variations of the attenuation are observed, which can reach even 200 dB/m at 3.5 MHz. In the second part of the report we present further development of the concept of the friction stir welding process monitoring by means of multiple sensors formed into a uniform circular array (UCA). After a brief introduction into modeling Lamb waves and UCA we focus on array processing techniques that enable estimating direction of arrival of multimodal Lamb waves. We consider two new techniques, the Capon beamformer and the broadband multiple signal classification technique (MUSIC). We present simulation results illustrating their performance. In the final part we present the phase shift migration algorithm for ultrasonic imaging of layered media using synthetic aperture concept. We start from explaining theory of the phase migration concept, which is followed by the results of experiments performed on copper blocks with drilled holes. We show that the proposed algorithm performs well for immersion inspection of metal objects and yields both improved spatial resolution and suppressed grain noise

  10. Inspection of copper canister for spent nuclear fuel by means of ultrasound. Copper characterization, FSW monitoring with acoustic emission and ultrasonic imaging

    International Nuclear Information System (INIS)

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in 2008. The first part of the report is concerned with aspects related to ultrasonic attenuation of copper material used for canisters. We present results of attenuation measurement performed for a number of samples taken from a real canister; two from the lid and four from different parts of canister wall. Ultrasonic attenuation of the material originating from canister lid is relatively low (less that 50 dB/m) and essentially frequency independent in the frequency range up to 5 MHz. However, for the material originating from the extruded canister part considerable variations of the attenuation are observed, which can reach even 200 dB/m at 3.5 MHz. In the second part of the report we present further development of the concept of the friction stir welding process monitoring by means of multiple sensors formed into a uniform circular array (UCA). After a brief introduction into modeling Lamb waves and UCA we focus on array processing techniques that enable estimating direction of arrival of multimodal Lamb waves. We consider two new techniques, the Capon beamformer and the broadband multiple signal classification technique (MUSIC). We present simulation results illustrating their performance. In the final part we present the phase shift migration algorithm for ultrasonic imaging of layered media using synthetic aperture concept. We start from explaining theory of the phase migration concept, which is followed by the results of experiments performed on copper blocks with drilled holes. We show that the proposed algorithm performs well for immersion inspection of metal objects and yields both improved spatial resolution and suppressed grain noise

  11. POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 110: AREA 3 WMD U-3AX/BL CRATER, NEVADA TEST SITE, NEVADA FOR THE PERIOD JULY 2004 - JUNE 2005

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-08-01

    This Post-Closure Inspection and Monitoring report provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 Waste Management Division (WMD) U-3ax/bl Crater. This report includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110, for the annual period July 2004 through June 2005. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, cover vegetation, perimeter fence, and use restriction warning signs was good. Settling was observed that exceeded the action level as specified in Section VII.B.7 of the Hazardous Waste Permit Number NEV HW009 (Nevada Division of Environmental Protection, 2000). This permit states that cracks or settling greater than 15 centimeters (cm) (6 inches [in]) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection.

  12. Hospital Inspections

    Data.gov (United States)

    U.S. Department of Health & Human Services — Welcome to hospitalinspections.org, a website run by the Association of Health Care Journalists (AHCJ) that aims to make federal hospital inspection reports easier...

  13. Process variation monitoring (PVM) by wafer inspection tool as a complementary method to CD-SEM for mapping field CDU on advanced production devices

    Science.gov (United States)

    Kim, Dae Jong; Yoo, Hyung Won; Kim, Chul Hong; Lee, Hak Kwon; Kim, Sung Su; Bae, Koon Ho; Spielberg, Hedvi; Lee, Yun Ho; Levi, Shimon; Bustan, Yariv; Rozentsvige, Moshe

    2010-03-01

    As design rules shrink, Critical Dimension Uniformity (CDU) and Line Edge Roughness (LER) have a dramatic effect on printed final lines and hence the need to control these parameters increases. Sources of CDU and LER variations include scanner auto-focus accuracy and stability, layer stack thickness, composition variations, and exposure variations. Process variations, in advanced VLSI production designs, specifically in memory devices, attributed to CDU and LER affect cell-to-cell parametric variations. These variations significantly impact device performance and die yield. Traditionally, measurements of LER are performed by CD-SEM or OCD metrology tools. Typically, these measurements require a relatively long time to set and cover only selected points of wafer area. In this paper we present the results of a collaborative work of the Process Diagnostic & Control Business Unit of Applied Materials and Hynix Semiconductor Inc. on the implementation of a complementary method to the CDSEM and OCD tools, to monitor defect density and post litho develop CDU and LER on production wafers. The method, referred to as Process Variation Monitoring (PVM) is based on measuring variations in the scattered light from periodic structures. The application is demonstrated using Applied Materials DUV bright field (BF) wafer inspection tool under optimized illumination and collection conditions. The UVisionTM has already passed a successful feasibility study on DRAM products with 66nm and 54nm design rules. The tool has shown high sensitivity to variations across an FEM wafer in both exposure and focus axes. In this article we show how PVM can help detection of Field to Field variations on DRAM wafers with 44nm design rule during normal production run. The complex die layout and the shrink in cell dimensions require high sensitivity to local variations within Dies or Fields. During normal scan of production wafers local Process variations are translated into GL (Grey Level) values

  14. Y-12 Groundwater Protection Program CY 2009 Triennial Report Of The Monitoring Well Inspection And Maintenance Program, Y-12 National Security Complex, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-06-01

    This document is the triennial report for the Well Inspection and Maintenance Program of the Y- 12 Groundwater Protection Program (GWPP), at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12). This report formally documents well inspection events conducted on active and inactive wells at Y-12 during calendar years (CY) 2007 through 2009; it documents well maintenance and plugging and abandonment activities completed since the last triennial inspection event (CY 2006); and provides summary tables of well inspection events, well maintenance events, and well plugging and abandonment events during the reference time period.

  15. Inspection of copper canister for spent nuclear fuel by means of ultrasound. FSW monitoring with emission, copper characterization and ultrasonic imaging

    Energy Technology Data Exchange (ETDEWEB)

    Stepinski, Tadeusz (ed.); Engholm, Marcus; Olofsson, Tomas (Uppsala Univ., Signals and Systems, Dept. of Technical Sciences, Uppsala (Sweden))

    2008-09-15

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in 2007. In the first part of the report we further develop the concept of monitoring of the friction stir welding (FSW) process by means of acoustic emission (AE) technique implemented using multiple sensors formed into a circular array. After a brief introduction into the field of arrays and beamforming we focus on the features of uniform circular arrays (UCA). Results obtained from the simulations of UCA beamformer based on phase mode concept are presented for the continuous wave as well as for the pulse, noise-free input signals. The influence of white noise corrupting the input pulse is also considered and a simple regularization technique proposed as a solution to this problem. The second part of the report is concerned with aspects related to ultrasonic attenuation of copper material used for canisters. We compare resonant ultrasound spectroscopy (RUS) with other methods used for characterization of the copper material. RUS is a non-destructive technique based on sensing mechanical resonances present in a tested sample in the ultrasonic frequency range. Resonance frequencies observed in a material sample (with given geometry) are directly related to the vibration modes occurring in the inspected volume defined by the material parameters (elastic constants). We solve the inverse problem that consists in using the information about resonance frequencies acquired in physical measurements for estimating material parameters. Our aim in this project is to investigate the feasibility of RUS for the grain size estimation in copper using copper specimens that were provided by SKB. In the final part we consider the design of input signals for ultrasonic arrays. The Bayesian linear minimum mean squared error (LMMSE) estimator discussed in our former reports is studied. We show that it

  16. Inspection of copper canister for spent nuclear fuel by means of ultrasound. FSW monitoring with emission, copper characterization and ultrasonic imaging

    International Nuclear Information System (INIS)

    This report contains the research results concerning advanced ultrasound for the inspection of copper canisters for spent nuclear fuel obtained at Signals and Systems, Uppsala University in 2007. In the first part of the report we further develop the concept of monitoring of the friction stir welding (FSW) process by means of acoustic emission (AE) technique implemented using multiple sensors formed into a circular array. After a brief introduction into the field of arrays and beamforming we focus on the features of uniform circular arrays (UCA). Results obtained from the simulations of UCA beamformer based on phase mode concept are presented for the continuous wave as well as for the pulse, noise-free input signals. The influence of white noise corrupting the input pulse is also considered and a simple regularization technique proposed as a solution to this problem. The second part of the report is concerned with aspects related to ultrasonic attenuation of copper material used for canisters. We compare resonant ultrasound spectroscopy (RUS) with other methods used for characterization of the copper material. RUS is a non-destructive technique based on sensing mechanical resonances present in a tested sample in the ultrasonic frequency range. Resonance frequencies observed in a material sample (with given geometry) are directly related to the vibration modes occurring in the inspected volume defined by the material parameters (elastic constants). We solve the inverse problem that consists in using the information about resonance frequencies acquired in physical measurements for estimating material parameters. Our aim in this project is to investigate the feasibility of RUS for the grain size estimation in copper using copper specimens that were provided by SKB. In the final part we consider the design of input signals for ultrasonic arrays. The Bayesian linear minimum mean squared error (LMMSE) estimator discussed in our former reports is studied. We show that it

  17. Bayesian Monitoring.

    OpenAIRE

    Kirstein, Roland

    2005-01-01

    This paper presents a modification of the inspection game: The ?Bayesian Monitoring? model rests on the assumption that judges are interested in enforcing compliant behavior and making correct decisions. They may base their judgements on an informative but imperfect signal which can be generated costlessly. In the original inspection game, monitoring is costly and generates a perfectly informative signal. While the inspection game has only one mixed strategy equilibrium, three Perfect Bayesia...

  18. Y-12 Groundwater Protection Program CY2012 Triennial Report Of The Monitoring Well Inspection And Maintenance Program Y-12 National Security Complex, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    This document is the triennial report for the Well Inspection and Maintenance Program of the Y- 12 Groundwater Protection Program (GWPP), at the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12). This report formally documents well inspections completed by the GWPP on active and inactive wells at Y-12 during calendar years (CY) 2010 through 2012. In addition, this report also documents well inspections performed under the Y-12 Water Resources Restoration Program, which is administered by URS|CH2M Oak Ridge (UCOR). This report documents well maintenance activities completed since the last triennial inspection event (CY 2009); and provides summary tables of well inspections and well maintenance activities during the reference time period.

  19. Inspection scheme

    International Nuclear Information System (INIS)

    As part of the Danish RERTR Program, three fuel elements with LEU U3O8-Al fuel and three fuel elements with LEU U3Si2-Al fuel were manufactured by NUKEM for irradiation testing in the DR-3 reactor at the Risoe National Laboratory in Denmark. The inspection scheme for the elements with U3O8-Al fuel is presented here as an illustration only. The inspection scheme for the elements with U3Si2-Al fuel was very similar. In this example, all document numbers, drawing numbers, and form numbers have been deleted or replaced with a generic identification. (author)

  20. Intelligent Monitoring? Assessing the ability of the Care Quality Commission’s statistical surveillance tool to predict quality and prioritise NHS hospital inspections

    OpenAIRE

    Griffiths, Alexander; Beaussier, Anne-Laure Marie Veronique; Demeritt, David Burgess; Rothstein, Henry Frederick

    2016-01-01

    Background The Care Quality Commission (CQC) is responsible for ensuring the quality of the health and social care delivered by more thanm 30 000 registered providers in England. With only limited resources for conducting on-site inspections, the CQC has used statistical surveillance tools to help it identify which providers it should prioritise for inspection. In the face of planned funding cuts, the CQC plans to put more reliance on statistical surveillance tools to assess risks to quality ...

  1. Post-Closure Inspection and Monitoring Report for Corrective Action Unit 110: Area 3 WMD U-3ax/bl Crater, Nevada Test Site, Nevada, For the Period July 2007-June 2008

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-08-01

    This Post-Closure Inspection and Monitoring Report (PCIMR) provides the results of inspections and monitoring for Corrective Action Unit (CAU) 110, Area 3 WMD [Waste Management Division] U-3ax/bl Crater. This PCIMR includes an analysis and summary of the site inspections, repairs and maintenance, meteorological information, and soil moisture monitoring data obtained at CAU 110 for the period July 2007 through June 2008. Site inspections of the cover were performed quarterly to identify any significant changes to the site requiring action. The overall condition of the cover, perimeter fence, and use restriction (UR) warning signs was good. However, settling was observed that exceeded the action level as specified in Section VII.B.7 of the Hazardous Waste Permit Number NEV HW021 (Nevada Division of Environmental Protection, 2005). This permit states that cracks or settling greater than 15 centimeters (6 inches) deep that extend 1.0 meter (m) (3 feet [ft]) or more on the cover will be evaluated and repaired within 60 days of detection. Two areas of settling and cracks were observed on the south and east edges of the cover during the September 2007 inspection that exceeded the action level and required repair. The areas were repaired in October 2007. Additional settling and cracks were observed along the east side of the cover during the December 2007 inspection that exceeded the action level, and the area was repaired in January 2008. Significant animal burrows were also observed during the March 2008 inspection, and small mammal trapping and relocation was performed in April 2008. The semiannual subsidence surveys were performed in September 2007 and March 2008. No significant subsidence was observed in the survey data. Monument 5 shows the greatest amount of subsidence (-0.02 m [-0.08 ft] compared to the baseline survey of 2000). This amount is negligible and near the resolution of the survey instruments; it does not indicate that subsidence is occurring overall on

  2. Comparison of recording of pericarditis and lung disorders at routine meat inspection with findings at systematic health monitoring in Danish finisher pigs

    DEFF Research Database (Denmark)

    Nielsen, Søren Saxmose; Nielsen, Gitte Blach; Denwood, Matt;

    2015-01-01

    purpose that is required of them. Routine meat inspection data were originally collected with the purpose of safeguarding food, but have been re-tasked to also include animal welfare assessment. The objective of the present study was to compare the recording of pericarditis, pleuritis and lungs with...... heart). Conclusions Overall, the results suggest that the correlation between findings at RMI and SHM was moderate for pleuritis and lungs with lesions, but poor for pericarditis. The latter could partly be explained by the type of meat inspection conducted at the abattoir. We conclude that caution...

  3. In-service inspection - a vital role in monitoring and health assessment of nuclear pressure vessels, piping and components at Tarapur Atomic Power Station - 1 and 2

    International Nuclear Information System (INIS)

    Tarapur Atomic Power Station is a twin unit Boiling Water Reactors (BWRs) built in 1960's and presently operating at 160MWe. TAPS has completed 36 years of successful commercial operation and is continuing to provide safe, economic and reliable power supply. The design life of Tarapur nuclear reactors is 40 Effective Full Power Years (EFPY). So far TAPS has completed about 20EFPY for each reactor. In order to estimate the healthiness of nuclear components, a comprehensive study was made by the station in consultation with design group of Nuclear Power Corporation of India Ltd.. In-Service Inspection (ISI) substantially enhances confidence in component performance. Consolidated inspection early in service life provides greater assurance of component's integrity. Periodic in-service inspection provides vital information in the form of flaw characterization for assessment of structural integrity. This paper describes various degradation mechanisms (SCC, IGSCC, TGSCC, EC, FAC etc.,) identified for critical components, their method of detection, methodologies followed for In-Service inspection and developmental activities to assess the integrity of nuclear reactor vessels, piping and components for continued service. Also a comprehensive examination carried out on Structures, Systems and Components (SSCs) as part of plant ageing management programme is also discussed. (author)

  4. Aspects of Inspection Planning

    DEFF Research Database (Denmark)

    Faber, M. H.; Sørensen, John Dalsgaard

    Inspection planning for systems is considered with special emphasis to the effect of the quality of inspections on the system reliability and the probability of repair. Inspection quality is described and discussed in terms of inspection reliability and inspection coverage where the latter is set...... theoretical framework for updating of the reliability of components and systems on the basis of inspection results is outlined. Systems representative for inspection planning of different engineering systems subjected to typical deterioration processes are presented. Numerical simulation studies are performed...... on the presented systems and the effect of inspection reliability and coverage is investigated for systems of different sizes. The results of the studies illustrate the effect of inspections in practical inspection problems and can be used as an initial guideline for selecting the quality of...

  5. In-service monitoring and fractographic inspection of ultrasonic indications on a feed water suction pipe of the Gundremmingen nuclear power plant

    International Nuclear Information System (INIS)

    Radiographic and ultrasonic examinations of three pipes of the Gundremmingen nuclear power plant revealed cracks with a maximum depth of about 2 mm on the inside of the pipes with a wall thickness of 7.1 mm. For continued service until replacement two representative areas were monitored for crack growth by means of the potential drop method. As crack growth during the last year of service can be excluded by metallographic examinations after replacement the result of monitoring by means of potential probes - in relation to its resolution capacity no crack growth in the period under monitoring - is confirmed. A final evaluation based on the actual crack depths results in minimum resolution of 0.2 and 0.5 mm in crack depth. The suitability of the potential drop method for in-service monitoring of existing indications for crack growth - even until replacement of the component, if necessary - could thus be demonstrated convincingly

  6. Monitor

    Data.gov (United States)

    US Agency for International Development — A custom-built, dual-language (English and Spanish) system (http://www.monitor.net.co/) developed by DevTech that debuted in January 2011. It features a central PMP...

  7. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    International Nuclear Information System (INIS)

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996

  8. Monitoring

    Czech Academy of Sciences Publication Activity Database

    Ložek, Vojen; Němec, J.

    Praha : Consult, 2003 - (Němec, J.), s. 111-115 ISBN 80-902132-4-3 Grant ostatní: Magistrát hlavního města Prahy(CZ) DAG/67/04/000176/2001 Institutional research plan: CEZ:AV0Z3013912 Keywords : monitoring * environmental quality * Prague Subject RIV: DB - Geology ; Mineralogy

  9. Monitoring

    Science.gov (United States)

    ... its main source of fuel. To keep your blood sugar level on target and avoid problems with your eyes, kidneys, heart and feet, you should eat right ... better. And monitoring doesn’t stop at measuring blood sugar levels. Because ... blood testing) Eye health (eye exams) Foot health (foot exams and ...

  10. Software Formal Inspections Guidebook

    Science.gov (United States)

    1993-01-01

    The Software Formal Inspections Guidebook is designed to support the inspection process of software developed by and for NASA. This document provides information on how to implement a recommended and proven method for conducting formal inspections of NASA software. This Guidebook is a companion document to NASA Standard 2202-93, Software Formal Inspections Standard, approved April 1993, which provides the rules, procedures, and specific requirements for conducting software formal inspections. Application of the Formal Inspections Standard is optional to NASA program or project management. In cases where program or project management decide to use the formal inspections method, this Guidebook provides additional information on how to establish and implement the process. The goal of the formal inspections process as documented in the above-mentioned Standard and this Guidebook is to provide a framework and model for an inspection process that will enable the detection and elimination of defects as early as possible in the software life cycle. An ancillary aspect of the formal inspection process incorporates the collection and analysis of inspection data to effect continual improvement in the inspection process and the quality of the software subjected to the process.

  11. Technical objectives of inspection

    International Nuclear Information System (INIS)

    The various technical objectives of inspection are discussed in a very general manner. The discussion includes how the inspection function is related to the assumed threat, the various degrees of assurance and reliance on criteria, and the hierarchy of assurance which is obtained from the various types or levels of inspection

  12. Inspection of licensee - Maintenance programme and activities

    International Nuclear Information System (INIS)

    An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

  13. Approximations in Inspection Planning

    DEFF Research Database (Denmark)

    Engelund, S.; Sørensen, John Dalsgaard; Faber, M. H.; Bloch, Allan

    2000-01-01

    . One of the more important of these approximations is the assumption that all inspections will reveal no defects. Using this approximation the optimal inspection plan may be determined on the basis of conditional probabilities, i.e. the probability of failure given no defects have been found by the......Planning of inspections of civil engineering structures may be performed within the framework of Bayesian decision analysis. The effort involved in a full Bayesian decision analysis is relatively large. Therefore, the actual inspection planning is usually performed using a number of approximations...... inspection. In this paper the quality of this approximation is investigated. The inspection planning is formulated both as a full Bayesian decision problem and on the basis of the assumption that the inspection will reveal no defects....

  14. Electric motor-drive multilink manipulator for core internal inspection

    Energy Technology Data Exchange (ETDEWEB)

    Shimazu, Akira; Akisada, Toshihiro; Tanaka, Shoichi; Tanaka, Koichi; Kato, Koji

    1988-03-01

    Fuji Electric has developed a large electric motor-drive multilink manipulator system. This system makes possible to inspect in detail almost all the structures in a reactor. This system is composed of a power manipulator, a monitoring manipulator, inspection device and a control system. With simple and easy operation, the system can automatically access the in-reactor structures to be inspected through the narrow space, avoiding the interseptive structures. This report describes an outline of the Manipulator.

  15. Tools for nuclear inspection

    International Nuclear Information System (INIS)

    IAEA nuclear inspectors have a range of high-tech tools at their disposal. Over the last decade, there have been significant improvements in the technology they use, mostly software advances make equipment more powerful and provide faster results. As they gather evidence, inspectors use a broad array of technologies, such as hand held radiation detectors and measurement instruments. Some instruments are used to search for nuclear and radioactive materials known to be associated with weapons making. Others can identify specific radioactive elements in samples that inspectors collect for fuller analysis in laboratories. Methods and equipment used include swipe sampling, multi-channel analyzers (MCAs), alloy detectors (ALEX), environmental monitoring instruments, digital video surveillance systems, satellite imagery and inspection databases. The IAEA has its own experts and facilities, through its Safeguards Analytical Laboratory in Austria, experienced in sample measurements and analysis. A 'Clean Laboratory' equipped with highly sensitive instruments including electron microscopes and mass-spectrometers is operational there. Network labs involved are in Australia, France, Germany, Japan, Russia, united Kingdom and the United States

  16. A study on improvements of inspection efficiency with remote transmission of inspection data

    International Nuclear Information System (INIS)

    Current information networks technology brought secure and convenient condition of information transmission, so that inspectorates intend to apply such technology to optimize current inspection efforts. IAEA established the Remote Monitoring Project (RMP) in 1996 and started to draft safeguards concepts, and approaches to refer the implementation of remote monitoring technology and to compromise with relationship between current inspection activities and the remote monitoring technologies. Although communications costs and conditions of secured communication should be further investigated, the technologies would have a possibility to reduce current inspection efforts. We would face at the step to study on the several issues such as what measures could be candidate to use, how much cost we needs, what kind of technical risks would be concerned, further improvements could be achieved by comparison with current inspection costs and effectiveness. This paper reports on the expectation points and relevant technical attention points which are related to apply unattended inspection system with remote data transmission to the flows and inventory verification of item and bulk facility, respectively, in order to improve inspection efforts. (author)

  17. Contineous inspection during fabrication

    International Nuclear Information System (INIS)

    The continuous inspection process is a method used in a Manufacturing plant in order to obtain a fast feed-back between inspection results and manufacturing process. It often requires a specific approach in design and a wide cooperation between Engineering and Manufacturing people. This method leads to additional advantages such as high motivation, and better quality knowledge. (orig.)

  18. Eddy-Current Inspection Of Tab Seals On Beverage Cans

    Science.gov (United States)

    Bar-Cohen, Yoseph

    1994-01-01

    Eddy-current inspection system monitors tab seals on beverage cans. Device inspects all cans at usual production rate of 1,500 to 2,000 cans per minute. Automated inspection of all units replaces visual inspection by microscope aided by mass spectrometry. System detects defects in real time. Sealed cans on conveyor pass near one of two coils in differential eddy-current probe. Other coil in differential eddy-current probe positioned near stationary reference can on which tab seal is known to be of acceptable quality. Signal of certain magnitude at output of probe indicates defective can, automatically ejected from conveyor.

  19. Distributed heterogeneous inspecting system and its middleware-based solution

    Institute of Scientific and Technical Information of China (English)

    黄理灿; 吴朝晖; 潘云鹤

    2003-01-01

    There are many cases when an organization needs to monitor the data and operations of its supervised departments, especially those departments which are not owned by this organization and are managed by their own information systems. Distributed Heterogeneous Inspecting System (DHIS) is the system an organization uses to monitor its supervised departments by inspecting their information systems. In DHIS, the inspected systems are generally distributed, heterogeneous, and constructed by different companies. DHIS has three key processes-abstracting core data sets and core operation sets, collecting these sets, and inspecting these collected sets. In this paper, we present the concept and mathematical definition of DHIS, a metadata method for solving the interoperability, a security strategy for data transferring, and a middleware-based solution of DHIS. We also describe an example of the inspecting system at WENZHOU custom.

  20. Distributed heterogeneous inspecting system and its middleware-based solution

    Institute of Scientific and Technical Information of China (English)

    黄理灿; 吴朝晖; 潘云鹤

    2003-01-01

    There are many cases when an organization needs to monitor the data and operations of its super-vised departments, especially those departments which are not owned by this organization and are managed by their own information systems. Distributed Heterogeneous Inspecting System (DHIS) is the system an organization uses to monitor its supervised departments by inspecting their information systems. In DHIS, the inspected systems are generally distributed, heterogeneous, and constructed by different companies. DHIS has three key processes-abstracting core data sets and core operation sets, collecting these sets, and inspecting these collected sets. In this paper, we present the concept and mathematical definition of DHIS, a metadata method for solving the interoperability, a security strategy for data transferring, and a middleware-based solution of DHIS. We also describe an example of the inspecting system at WENZHOU custom.

  1. Magnetic rubber inspection (MRI)

    International Nuclear Information System (INIS)

    Magnetic Rubber Inspection (MRI) was developed to inspect for small cracks and flaws encountered in high performance aircraft. A formula of very fine magnetic particles immersed in a room temperature curing rubber is catalysed and poured into dams (retainers) on the surface of the part to be inspected. Inducing a magnetic field then causes the particles to be drawn to discontinuities in the component under test. These indicating particles are held to the discontinuity by magnetic attraction, as the rubber cures. The solid rubber cast (Replica) is then removed and examined under a microscope for indicating lines of particle concentrations. 3 refs., 6 figs

  2. Identification of areas and time intervals for inservice inspections

    International Nuclear Information System (INIS)

    Inservice inspections are an important, redundant part of the overall concept for ensuring component integrity during NPP operation. Their efficiency however has to be considered in the context of measures creating required component quality (design and manufacture), and inspection and monitoring measures maintaining the quality of components. If an available system for inservice monitoring yields comprehensive information about real inservice loads (monitoring of the causes of degradation), inservice inspections can be designed to purposefully check the possibly resulting damaging modes and defects. If there is no or only low-level monitoring, the possible consequences of possibly damaging mechanisms that may be unknown should be checked by expanded inservice inspections plus, if necessary, unspecific, random inspections. For selection of inspection areas and determination of inspection intervals, use of design-based analyses which take into account conservative, specified loads and load frequencies (for operating modes and incidents) is not recommendable. The recommended approach is to take as a basis information on measured, real inservice loads together with information about the real quality status of components, derived from manufacturing data and service histories. The available information has to be scanned and processed so as to give a basis for new appraisal of hitherto applied NDE methods. (orig./CB)

  3. Risk-Informed Decisions Optimization in Inspection and Maintenance

    International Nuclear Information System (INIS)

    partial case is used for the construction and research of the models related to inspections and maintenance planning of Ignalina Nuclear Power Plant (RBMK-1500) piping components. The discussed example is related to risk analysis and inspection program improvements for selected pipe systems. The new risk-informed inspection and maintenance program for selected pipe systems are compared with various alternatives. The usage of risk evaluations to optimize the selection of inspection locations, the inspection interval, and the changes in risk and cost due suggested modifications are demonstrated. The proposed integrated modeling methodic and general model of inspection process can be used as a base for other risk-informed models of inspection process control and risk monitors of complex dynamic systems. (authors)

  4. Guidelines for software inspections

    Science.gov (United States)

    1983-01-01

    Quality control inspections are software problem finding procedures which provide defect removal as well as improvements in software functionality, maintenance, quality, and development and testing methodology is discussed. The many side benefits include education, documentation, training, and scheduling.

  5. Wedges for ultrasonic inspection

    Energy Technology Data Exchange (ETDEWEB)

    Gavin, Donald A. (Rexford, NY)

    1982-01-01

    An ultrasonic transducer device is provided which is used in ultrasonic inspection of the material surrounding a threaded hole and which comprises a wedge of plastic or the like including a curved threaded surface adapted to be screwed into the threaded hole and a generally planar surface on which a conventional ultrasonic transducer is mounted. The plastic wedge can be rotated within the threaded hole to inspect for flaws in the material surrounding the threaded hole.

  6. Source Inspection Scheduling Calendar

    Science.gov (United States)

    Hollis, Brayden

    2011-01-01

    Quality is an essential component for creating flight hardware travelling through space since the hardware is extremely expensive and cannot be reworked or repaired once launched. An important step in this process is ensuring the quality of hardware procured from Jet Propulsion Laboratory's (JPL) suppliers. An important element of determining supplier quality is source inspection. Source inspections are performed at suppliers' facilities by JPL employeesto ensure that hardware characteristics are acceptable before being covered up and/or delivered to JPL.

  7. Inspection of tendons

    International Nuclear Information System (INIS)

    There is no reliable inspection method of tendons in use in Finland. In this research an inspection method was developed which can be applied when the sheath is of metallic material. The sheath is first revealed using a core cutter. A hole is then picked on the sheath and the condition of the injection grout and the tendons are inspected using an endoscope. A camera may be attached to the endoscope. To prevent the sheath from damaging during drilling a protective voltage is connected to the drill and the sheath is earthed. When the cutting edge hits the sheath the electric current is disconnected automatically. Experiments were made with the inspection method on three bridges one of which was still under construction and had no superstructure, one had just been constructed and one was 29 years old. The drillings for inspection were carried out on the top of the decks. The method worked as planned in all cases. In section 6 an example of corrosion classification is given which may be used when estimating whether the corrosion weakens the bearing capacity of the inspected tendons or not. (au) (1 ref., 25 figs.)

  8. Visual inspection device for reactor inside

    International Nuclear Information System (INIS)

    The present invention concerns a submerged type inspection device for visually inspecting structures and equipments such as a reactor pressure vessel, fuel pool, etc. That is, this device comprises a vehicle which moves in the reactor structure, a control device for controlling the water vehicle in water and a cable which connects both of them. The water vehicle comprises a TV camera with focus control function and tilting function, a depth gauge, an angular velocity gauge, a submerged illumination light, a position fixing device and a plurality of propulsion devices. The water vehicle of the visual inspection device for the inside of the reactor is put into the reactor structure filled with water. Each propulsion device is controlled by the control device and water vehicle is brought closer to an object. Then, pictures are taken by the TV and with the submerged illumination light, which are displayed on a monitor. (I.S.)

  9. Improvements in in-bay irradiated fuel inspection planning and analysis at Bruce Power

    International Nuclear Information System (INIS)

    This paper describes improvements in irradiated fuel inspection planning and analysis implemented at Bruce Power since 2012. A review of inspection plans and fuel performance reports since 2001 identified significant variations in how irradiated fuel bundles were selected for inspection from year-to-year. A series of inspection tasks was established in an inspection logic and technical basis document. Inspection objectives and bundle selection criteria were defined for each task. These requirements, along with resource availability are now used to prepare a fuel inspection plan each year. The inspection results are then considered in the context of the analysis objectives for each task. The inspection results are presented in brief monthly updates and in-depth semi-annual reports in addition to the Annual Fuel Performance Reports. These changes have improved the effectiveness, consistency and efficiency of Bruce Power’s fuel performance monitoring. (author)

  10. Optimizing pre-service inspection data

    International Nuclear Information System (INIS)

    The phenomenon of intergranular stress corrosion cracking (IGSCC) in nuclear power plant piping systems has been the single biggest factor in an evolution that has changed and continues to change in-service inspection practices and philosophy throughout the industry. In-service inspection has been found to deal with several distinct phases of the problem. At the onset, existing technology was demonstrated to be unable to detect IGSCC adequately. This inability to detect IGSCC was soon overcome. However, it immediately pointed out the difficulties associated with the discrimination between IGSCC and other harmless metallurgical conditions. On the heels of detection and discrimination came problems associated with determining crack size and the monitoring of overlayed flaws. A wealth of information has been written on all phases of IGSCC; however, one particular aspect has as of yet seen little attention. With an increasing number of plants choosing to replace flawed pipe, the pre-service inspection of the replaced piping demands increased attention. The lessons learned through inspection for IGSCC need again to be applied to the replacement piping. Through increased attention at installation, many of the difficulties associated with proper inservice inspection may be reduced or eliminated, thereby realizing an economy in outage scheduling, personnel exposure, and, overall, a more reliable in-service examination

  11. Inspection Strategies for Concrete Bridges

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Thoft-Christensen, Palle

    In this paper an optimal inspection strategy for concrete bridges based on periodic routine and detailed inspections is presented. The failure mode considered is corrosion of the reinforcement due to chlorides. A simple modelling of the corrosion and of the inspection strategy is presented. The...... optimal inspection strategy is determined from an optimization problem, where the design variables are time intervals between detailed inspections and the concrete cover. The strategy is illustrated on a simple structure, namely a reinforced concrete beam....

  12. Inspection practice and a role of TSO

    International Nuclear Information System (INIS)

    Technical and Scientific Support Organisations (TSOs) are not only expert organisations helping operators to fulfil the legal obligations but they can perform at least five tasks related to regulatory authority activities. Namely, TSOs can be an expert support when preparing legislation or guidelines. They can provide specific technical service e.g. providing independent monitoring of radioactivity in the environment or monitoring of foodstuff. They can also provide valuable data to regulatory authorities because they follow the achievements of science and technologies i.e. they are familiar with best available techniques and technologies. In many cases TSOs can be a pool of future employees of regulatory authorities and TSOs are expert or technical support at on-site inspections. Involvement of TSOs in on-site inspections either foreseen inspections or interventions requires very well defined roles of all organisations involved. Regarding the experiences of the Slovenian Nuclear Safety Administration the involvement of TSOs in on-site inspections is very beneficial to all stakeholders and leads not only to less financial and other burdens posed on the owner of sources but also basic safety requirements are implemented efficiently. (author)

  13. Piping inspection round robin

    International Nuclear Information System (INIS)

    The piping inspection round robin was conducted in 1981 at the Pacific Northwest National Laboratory (PNNL) to quantify the capability of ultrasonics for inservice inspection and to address some aspects of reliability for this type of nondestructive evaluation (NDE). The round robin measured the crack detection capabilities of seven field inspection teams who employed procedures that met or exceeded the 1977 edition through the 1978 addenda of the American Society of Mechanical Engineers (ASME) Section 11 Code requirements. Three different types of materials were employed in the study (cast stainless steel, clad ferritic, and wrought stainless steel), and two different types of flaws were implanted into the specimens (intergranular stress corrosion cracks (IGSCCs) and thermal fatigue cracks (TFCs)). When considering near-side inspection, far-side inspection, and false call rate, the overall performance was found to be best in clad ferritic, less effective in wrought stainless steel and the worst in cast stainless steel. Depth sizing performance showed little correlation with the true crack depths

  14. Safety System functional inspections

    International Nuclear Information System (INIS)

    The basic purpose of Safety System Functional Inspections (SSFI) is to carry out an impartial and independent assessment of previously selected safety systems, in order to determine whether they have been installed, tested, operated and managed in accordance with the original Design Bases and with the applicable regulatory requirements, codes and standards, that is, their Licensing Bases. These functional inspections are performed within the framework established by the Quality Assurance Programmes of electric utility owners, and in accordance with specifically prepared procedures previously approved for each power plant. These SSFIs verify, for safety systems and their support systems (eg HVAC systems, etc), the operational availability of inspected systems of components by researching and determining whether there have been generic or programmed deficiencies in the course of Operation, that will prevent the systems from adequately performing the functions for which they were originally designed. PSA and IPE results are used as the basis for selecting the systems that should undergo functional inspections. As a consequence of these SSFIs, final reports will be prepared, summarizing actions taken at the plants and contemplating discrepancies or deviations detected during inspection. The necessary corrective actions for these discrepancies will be indicated in either the design documentation or the Operation and Maintenance Procedures. (Author)

  15. Inspection device in liquid

    International Nuclear Information System (INIS)

    The present invention provides an inspection device in PWR reactor core in which inspection operations are made efficient by stabilizing a posture of the device in front-to-back, vertical and left-to-right directions by a simple structure. When the device conducts inspection while running in liquid, the front and the back directions of the device main body are inspected using a visual device while changing the posture by operating a front-to-back direction propulsion device and a right-to-left direction propulsion device, and a vertical direction propulsion device against to rolling, pitching and yawing of the device main body. In this case, a spherical magnet moves freely in the gravitational direction in a vibration-damping fluid in a non-magnetic spherical shell following the change of the posture of the device main body, in which the vibrations due to the movement of the spherical magnet is settled by the vibration-damping fluid thereby stabilizing the posture of the device main body. At a typical inspection posture, the settling effect is enhanced by the attraction force between the spherical magnets in the spherical shell and each of magnetic force-attracted magnetic members disposed to the outer circumference of the shell, and the posture of the device main body can be confirmed in front-to-back, right-to-left and vertical directions by each of the posture confirming magnetic sensors. (N.H.)

  16. CTBT on-site inspections

    Energy Technology Data Exchange (ETDEWEB)

    Zucca, J. J. [Principal Deputy, Global Security Directorate, Lawrence Livermore National Laboratory, Livermore, California (United States)

    2014-05-09

    On-site inspection (OSI) is a critical part of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The OSI verification regime provides for international inspectors to make a suite of measurements and observations on site at the location of an event of interest. The other critical component of the verification regime is the International Monitoring System (IMS), which is a globally distributed network of monitoring stations. The IMS along with technical monitoring data from CTBT member countries, as appropriate, will be used to trigger an OSI. After the decision is made to carry out an OSI, it is important for the inspectors to deploy to the field site rapidly to be able to detect short-lived phenomena such as the aftershocks that may be observable after an underground nuclear explosion. The inspectors will be on site from weeks to months and will be working with many tens of tons of equipment. Parts of the OSI regime will be tested in a field exercise in the country of Jordan late in 2014. The build-up of the OSI regime has been proceeding steadily since the CTBT was signed in 1996 and is on track to becoming a deterrent to someone considering conducting a nuclear explosion in violation of the Treaty.

  17. Ball screw inspection setup

    Science.gov (United States)

    Janusz, Rzepka; Sambor, Slawomir; Pienkowski, Janusz; Bielenin, Marcin

    2003-05-01

    In the following paper we describe arrangements of laser interferometer for investigation of screws and for inspection of ball screws. We have constructed two of them, namely: the technological setup for investigations of screw in process of production and the ball screw inspection setup. The former one is used to measure the pitch of screws. The data gathered during measurement is used to calculate the parameters for grinding machine. The later setup is used for testing parameters of complete ball screws. The software supporting this setup makes calculation of parameters of tested ball screw and creation of reports possible. Additionally, the inspection setup is the one that the torque measuring arrangements have been integrated on. Both the arrangements and the software allow for measurements of all parameters during movement of nut in full travel length of the ball screw and make charts and reports.

  18. Advances in inspection automation

    Science.gov (United States)

    Weber, Walter H.; Mair, H. Douglas; Jansen, Dion; Lombardi, Luciano

    2013-01-01

    This new session at QNDE reflects the growing interest in inspection automation. Our paper describes a newly developed platform that makes the complex NDE automation possible without the need for software programmers. Inspection tasks that are tedious, error-prone or impossible for humans to perform can now be automated using a form of drag and drop visual scripting. Our work attempts to rectify the problem that NDE is not keeping pace with the rest of factory automation. Outside of NDE, robots routinely and autonomously machine parts, assemble components, weld structures and report progress to corporate databases. By contrast, components arriving in the NDT department typically require manual part handling, calibrations and analysis. The automation examples in this paper cover the development of robotic thickness gauging and the use of adaptive contour following on the NRU reactor inspection at Chalk River.

  19. NRU light water reflector inspections

    International Nuclear Information System (INIS)

    In 2009 May, the National Research Universal (NRU) calandria leaked. In the next year the calandria was inspected with six new techniques, repaired, and the repair inspected with four additional new techniques. The calandria is surrounded by a light water reflector vessel. Concerns that the same corrosion mechanism may have damaged the reflector vessel led to plans to inspect the full circumference of the reflector wall for corrosion damage, through a 64 mm diameter port, from 10 m away, while inspecting from the corroded surface. The ultrasonic technique is intended to produce a very fine inspection grid, through the corroded surface, using a very small probe body over the approximately 5 m2 to be inspected. The calandria vessel inspections were successfully performed, in a short time period, under difficult conditions. This paper will discuss Operating Experience (OPEX) from the 2009/2010 calandria wall inspections and industry dialogue that were applied to the Reflector Wall Inspection (RWI) project. Interaction with the CANDU Inspection Qualification Bureau (CIQB) on procedures, training plans, and mock-up training, led to improvements in how these activities were performed for the RWI project. Experience with shift turnover meetings led to improvements in how the inspection team captures lessons learned, trends issues, and eliminates reoccurring design and procedure problems. Experience with collected and analyzed data, inspection shift logs, and video captured from inspections and repairs, were used to improve inspection performance. Finally, OPEX from radiation/activation and the calibration process reduced dose through tool design and procedure changes. (author)

  20. APPLYING SIMPLE TECHNOLOGY ACCOMPLISHES VISUAL INSPECTION CHALLENGES

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, C

    2007-07-21

    This paper discusses the successful implementation of simple video technologies at the Savannah River Site (SRS) to perform complex visual inspection, monitoring, and surveillance tasks. Because SRS facilities are similar to those of an industrial plant, the environmental and accessibility considerations for remote viewing are the primary determining factors in the selection of technology. The constraints and challenges associated with remote viewing are discussed, and examples of applications are given.

  1. Federal environmental inspections handbook

    International Nuclear Information System (INIS)

    This Federal Environmental Inspection Handbook has been prepared by the Department of Energy (DOE), Office of Environmental Guidance, RCRA/CERCLA Division (EH-231). It is designed to provide DOE personnel with an easily accessible compilation of the environmental inspection requirements under Federal environmental statutes which may impact DOE operations and activities. DOE personnel are reminded that this Handbook is intended to be used in concert with, and not as a substitute for, the Code of Federal Regulations (CFR). Federal Register (FR), and other applicable regulatory documents

  2. Inspection and test planning

    International Nuclear Information System (INIS)

    Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

  3. Inspection of Emergency Arrangements

    International Nuclear Information System (INIS)

    The Working Group on Inspection Practices (WGIP) was tasked by the NEA CNRA to examine and evaluate the extent to which emergency arrangements are inspected and to identify areas of importance for the development of good inspection practices. WGIP members shared their approaches to the inspection of emergency arrangements by the use of questionnaires, which were developed from the requirements set out in IAEA Safety Standards. Detailed responses to the questionnaires from WGIP member countries have been compiled and are presented in the appendix to this report. The following commendable practices have been drawn from the completed questionnaires and views provided by WGIP members: - RBs and their Inspectors have sufficient knowledge and information regarding operator's arrangements for the preparedness and response to nuclear emergencies, to enable authoritative advice to be given to the national coordinating authority, where necessary. - Inspectors check that the operator's response to a nuclear emergency is adequately integrated with relevant response organisations. - Inspectors pay attention to consider the integration of the operator's response to safety and security threats. - The efficiency of international relations is checked in depth during some exercises (e.g. early warning, assistance and technical information), especially for near-border facilities that could lead to an emergency response abroad. - RB inspection programmes consider the adequacy of arrangements for emergency preparedness and response to multi-unit accidents. - RBs assess the adequacy of arrangements to respond to accidents in other countries. - The RB's role is adequately documented and communicated to all agencies taking part in the response to a nuclear or radiological emergency. - Inspectors check that threat assessments for NPPs have been undertaken in accordance with national requirements and that up-to-date assessments have been used as the basis for developing emergency plans for

  4. Inspection Technology, Detection and Compliance: Evidence from Florida Restaurant Inspections

    OpenAIRE

    Jin, Ginger Zhe; Lee, Jungmin

    2013-01-01

    In this article, we show that a small innovation in inspection technology can make substantial differences in inspection outcomes. For restaurant hygiene inspections, the state of Florida has introduced a handheld electronic device, the portable digital assistant (PDA), which reminds inspectors of 1,000 potential violations that may be checked for. Using inspection records from July 2003 to June 2009, we find that the adoption of PDA led to 11% more detected violations and subsequently restau...

  5. Additive Manufacturing Infrared Inspection

    Science.gov (United States)

    Gaddy, Darrell

    2014-01-01

    Additive manufacturing is a rapid prototyping technology that allows parts to be built in a series of thin layers from plastic, ceramics, and metallics. Metallic additive manufacturing is an emerging form of rapid prototyping that allows complex structures to be built using various metallic powders. Significant time and cost savings have also been observed using the metallic additive manufacturing compared with traditional techniques. Development of the metallic additive manufacturing technology has advanced significantly over the last decade, although many of the techniques to inspect parts made from these processes have not advanced significantly or have limitations. Several external geometry inspection techniques exist such as Coordinate Measurement Machines (CMM), Laser Scanners, Structured Light Scanning Systems, or even traditional calipers and gages. All of the aforementioned techniques are limited to external geometry and contours or must use a contact probe to inspect limited internal dimensions. This presentation will document the development of a process for real-time dimensional inspection technique and digital quality record of the additive manufacturing process using Infrared camera imaging and processing techniques.

  6. 14 CFR 91.409 - Inspections.

    Science.gov (United States)

    2010-01-01

    ... detail— (i) An explanation of the progressive inspection, including the continuity of inspection... the name and address of the person responsible for scheduling the inspections required by the...

  7. Ultrasonic inspection methodology

    International Nuclear Information System (INIS)

    Steam generator tubes are known to be susceptible to stress corrosion cracking (SCC). Primary water SCC (PWSCC) and more recently secondary water SCC (SWSCC) have been observed in some Belgian plants. To help dealing with these problems, Laborelec developed an ultrasonic (UT) inspection system. It has been used for the last two years on a sampling basis in several plants. The field and laboratory measurements confirmed the advantage of using UT for the early detection of small circumferential cracks while an excellent correlation was demonstrated between eddy current RPC and UT for axial PWSCC. In conclusion: The latest in-service inspections demonstrated an average measurement cycle of 50 to 60 seconds per tube including the manipulator displacement from tube to tube. A sample of about 250 tubes with axial cracks was measured on-site with the eddy current RPC technique and the new UT system. All the UT measured lengths were within ± 1.5 mm of the RPC results. The same results were obtained from the inspection of the tubes repaired with the nickel process (Doel 3). Some indications of circumferential secondary side stress corrosion cracking were recently observed. A comparison with the eddy current rotating pancake coil confirmed the improved detectability of the UT system. The field and laboratory results obtained with this UT inspection system demonstrated the advantage of applying the ultrasonic technique for the detection and sizing of small volume cracks like SCC. Also, the small focal spot of the UT beam provided a clear advantage for the detection of circumferential PWSCC in the presence of multiple axial cracks. With an average rate dose to 60 tubes per hour for the top of the tubesheet area, this UT system can be considered as an industrial tool for the inspection of steam generator tubes

  8. Big Lake Dam Inspection Report

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This report summarizes an inspection of the Big Lake Dam that was done in September of 1983. The inspection did not reveal any conditions that constitute and...

  9. Visual inspection of vessel internals

    International Nuclear Information System (INIS)

    Visual inspection has matured to a qualified testing method and has become a standard method for inspection of reactor pressure vessels. Until today, all known defects in RPV internals have been detected by visual inspection. The codes KTA 3204 and DIN 25435-4 describe the framework conditions and requirements for visual inspections, which should be adhered to to the most possible extent. Visual inspections are carried by now at all RPV internals, also at those where access is difficult and limited. The inspection robot SUSI is applied in most cases. The camera and manipulator technology meanwhile has been upgraded to a standard performance quality allowing reliable, fast and easy visual inspection. The personnel is trained accordingly, so as to keep abreast with enhancements. Qualification of the inspection system has been simplified and standardised to a large extent. (orig/CB)

  10. On-site inspections: The ultimate verification measure

    International Nuclear Information System (INIS)

    Having existed for a mere six weeks in 2008, the State of Arcania was short-lived. The fictitious state helped to test on-site inspections, a key element of a global alarm system that monitors the Earth for signs of nuclear explosions. The Preparatory Commission for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) is mandated to build this system to verify States' compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). On-site inspections (OSI ) complement the verification regime's other elements: the International Monitoring System with its network of 337 facilities, the International Data Centre with its extensive data analysis capacities, and the Global Communications Infrastructure. On-site inspections can be invoked only after the Treaty's entry into force. A Member State may request an inspection should the analysis of monitoring data indicate that a nuclear explosion was carried out in violation of the CT BT. Facts gathered directly on the ground during an inspection will help States to establish whether or not a nuclear explosion did indeed take place. Thus, on-site inspections constitute the final verification measure under the Treaty.

  11. Optical inspection of NGL masks

    Science.gov (United States)

    Pettibone, Donald W.; Stokowski, Stanley E.

    2004-12-01

    For the last five years KLA-Tencor and our joint venture partners have pursued a research program studying the ability of optical inspection tools to meet the inspection needs of possible NGL lithographies. The NGL technologies that we have studied include SCALPEL, PREVAIL, EUV lithography, and Step and Flash Imprint Lithography. We will discuss the sensitivity of the inspection tools and mask design factors that affect tool sensitivity. Most of the work has been directed towards EUV mask inspection and how to optimize the mask to facilitate inspection. Our partners have succeeded in making high contrast EUV masks ranging in contrast from 70% to 98%. Die to die and die to database inspection of EUV masks have been achieved with a sensitivity that is comparable to what can be achieved with conventional photomasks, approximately 80nm defect sensitivity. We have inspected SCALPEL masks successfully. We have found a limitation of optical inspection when applied to PREVAIL stencil masks. We have run inspections on SFIL masks in die to die, reflected light, in an effort to provide feedback to improve the masks. We have used a UV inspection system to inspect both unpatterned EUV substrates (no coatings) and blanks (with EUV multilayer coatings). These inspection results have proven useful in driving down the substrate and blank defect levels.

  12. From Inspection to School Improvement? Evaluating the Accelerated Inspection Programme in Waltham Forest.

    Science.gov (United States)

    Hopkins, David; Harris, Alma; Watling, Rob; Beresford, John

    1999-01-01

    Outlines the main findings from the evaluation of the Accelerated Inspection Programme (AIP) in Waltham Forest under three main phases (pre-inspection, inspection, and post inspection). Focuses on the relationship between inspection and school improvement. Discusses the recommendations. (CMK)

  13. Overview of the software inspection process

    Energy Technology Data Exchange (ETDEWEB)

    Lane, G.L.; Dabbs, R. [Sandia National Labs., Albuquerque, NM (United States)

    1997-11-01

    This tutorial introduces attendees to the Inspection Process and teaches them how to organize and participate in a software inspection. The tutorial advocates the benefits of inspections and encourages attendees to socialize the inspection process in their organizations.

  14. Study of the relationship between nuclear safety and inspection

    International Nuclear Information System (INIS)

    In this study, a relationship between nuclear safety and inspection/monitoring was discussed. As a result of consideration, the followings were made clear. (1) Nuclear safety is secured by the combination of safety functions of nuclear plant system and plant managements by the human system including plant operator's organization. (2) Nuclear plant systems should be managed for each safety system because safety functions are fulfilled for each safety system. (3) The integrity of concerned system in the future can be evaluated only by the combination of inspection/monitoring and ageing degradation evaluation. (4) Inspection and monitoring is positioned as one of activities in plant management by the human system. (5) The two step method to evaluate the system integrity by using the large and local area evaluation approach can be considered to be reliable and reasonable. (author)

  15. Inspection and teachers’ emotions: An emotional evaluation of inspection

    Directory of Open Access Journals (Sweden)

    Binali Tunç

    2015-02-01

    Full Text Available In the study, inspection is discussed in relation to the teachers’ feelings and emotions it creates before inspection, during inspection and after inspection process. Teacher’s emotions have been investigated intentionally as emotional side of education has been neglected. Education is closely related to the emotions of teachers, who are the most important producers of educational activities.Educational activities are reduced to standard activities and defined with simple explanations or single labels such as ‘good-bad’, ‘successful-unsuccessful’, ‘adequate-inadequate’. Inspection causes emotions to be neglected. Moreover, recently, it has been discussed that there are approaches and systems that suggest constant and multi-dimensional inspection instead of traditional inspection.Qualitative research model was used to understand of teacher emotions. A semi structured form was used for the 38 primary school teachers’ interviews. After teacher interviews were completed, we analyzed and compared the interviews. Participants’ expressions were checked in terms of correctness, potential validity and reliability problems such as misinterpretation.   The results of the study can be summarized as follows: There were no positive expressions related to the emotional impact of inspection on teachers. In addition, teachers felt that the inspectors were stressed, anxious, uneasy, accusatory, coercive, looking for defect and areas of unsuccessful teaching performance. Most of teachers reported that being observed and evaluated caused them to have negative emotions.Teachers’ perceptions about inspection are found to be negative. There are no statements that indicate there is a positive impression of inspection on teachers. The emotions that are experienced before inspection: pressure, hurry, stress, concern, tension, anxiety, worry, uncertainty; during inspection: stress, tension, anger, loss of strength, humiliation and lack of self

  16. Optimizing in-service inspection

    International Nuclear Information System (INIS)

    In the present paper, the aspects of optimizing In-Service Inspection (ISI) is discussed. Slovenian Nuclear Safety Administration (SNSA) and its authorized organization for the ISI activities, Institute of Metals and Technologies, are permanently involved in the ISI process of the nuclear power plant (NPP) Krsko. Based on this experience and additionally gathered by reviewing of the new ISI program, the decision was made to improve recent regulatory and professional practice. Traditional criteria, standards and practice are bases for the further improvements. Improvements will be done by adding a new knowledge about the safety important components of the systems to the basic practice. It is necessary to identify conditions of the safety important components, such as realistic stress and fatigue conditions, material properties changes due aging processes, the temperature cycling effects, existing flaws characterization in the light of the previous detection and equipment technique used, assessment of the measurement accuracy on the results etc. In addition to the above mentioned, risk assessment and evaluation of the whole ISI shall be done. To do this it is necessary to make risk evaluation, based on previous structural element probability assessment. Probabilistic risk assessment is important and one of the most powerful tools in the ISI optimization. Some basic work in the field of the risk informed methods related to the nuclear safety components has been already done. Based on reference documentation, the most important steps in risk informed ISI are discussed. Those steps are scope definition, consequence evaluation, failure probability estimation, risk evaluation, nondestructive examination method selection and possibilities of implementation, monitoring and feedback. Recent experience on the ISI in the nuclear world show that such practice is very important during ISI decision making process and has some measurable effects too. It is clear that classical

  17. Eddy current inspection methodology

    International Nuclear Information System (INIS)

    World-wide operating experience with nuclear pressurized water reactors shows that most steam generators show evidence of major degradation phenomena. Laborelec has designed several automated inspection systems using eddy current (bobbin coil, pancake coils and rotating coil) and ultrasound techniques. The bobbin coil is mostly used as a fast and global detection method while dedicated sensors, like the rotating pancake coil, are applied for an improved defect characterization. Experience has demonstrated that significant advantages in accuracy, reliability and cost are intimately related to the automation process. In conclusion: The concept of a multipurpose inspection system satisfies the safety goal and the utility requirements for reliability, accuracy and lower costs. An optimum was reached by equipment modularity, computer control and integrated design of sensors and instrumentation. What previously required several man-weeks of work is now achieved within a few hours time. With a presently unparalleled field performance, Laborelec has set the basis of new industrial standards

  18. Pressurized water reactor inspection procedures

    International Nuclear Information System (INIS)

    Inspections of the reactor pressure vessels of pressurized water reactors (PWR) so far used to be carried out with different central mast manipulators. For technical reasons, parallel inspections of two manipulators alongside work on the refueling cavity, so as to reduce the time spent on the critical path in a revision outage, are not possible. Efforts made to minimize the inspection time required with one manipulator have been successful, but their effects are limited. Major reductions in inspection time can be achieved only if inspections are run with two manipulators in parallel. The decentralized manipulator built by GEC Alsthom Energie and so far emmployed in boiling water reactors in the USA, Spain, Switzerland and Japan allows two systems to be used in parallel, thus reducing the time required for standard inspection of a pressure vessel from some six days to three days. These savings of approximately three days are made possible without any compromises in terms of positioning by rail-bound systems. During inspection, the reactor refueling cavity is available for other revision work without any restrictions. The manipulator can be used equally well for inspecting standard PWR, PWR with a thermal shield, for inspecting the land between in-core instrumentation nozzles, BWR with and without jet pumps (complementary inspection), and for inspecting core support shrouds. (orig.)

  19. NRU light water reflector inspections

    Energy Technology Data Exchange (ETDEWEB)

    Lumsden, R.H.; Hebert, H.; Zahn, N.; Simpson, N.W. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2011-07-01

    In 2009 May, the National Research Universal (NRU) calandria leaked. In the next year the calandria was inspected with six new techniques, repaired, and the repair inspected with four additional new techniques. The calandria is surrounded by a light water reflector vessel. Concerns that the same corrosion mechanism may have damaged the reflector vessel led to plans to inspect the full circumference of the reflector wall for corrosion damage, through a 64 mm diameter port, from 10 m away, while inspecting from the corroded surface. The ultrasonic technique is intended to produce a very fine inspection grid, through the corroded surface, using a very small probe body over the approximately 5 m{sup 2} to be inspected. The calandria vessel inspections were successfully performed, in a short time period, under difficult conditions. This paper will discuss Operating Experience (OPEX) from the 2009/2010 calandria wall inspections and industry dialogue that were applied to the Reflector Wall Inspection (RWI) project. Interaction with the CANDU Inspection Qualification Bureau (CIQB) on procedures, training plans, and mock-up training, led to improvements in how these activities were performed for the RWI project. Experience with shift turnover meetings led to improvements in how the inspection team captures lessons learned, trends issues, and eliminates reoccurring design and procedure problems. Experience with collected and analyzed data, inspection shift logs, and video captured from inspections and repairs, were used to improve inspection performance. Finally, OPEX from radiation/activation and the calibration process reduced dose through tool design and procedure changes. (author)

  20. Proposal of inspection methodology for environment radiological control

    International Nuclear Information System (INIS)

    The Radiation Protection and Dosimetry Institute (IRD) of the Brazilian Nuclear Energy Commission (CNEN) is in charge of verifying that the self-monitoring operator is effective to control the radiological quality of environmental around the nuclear facilities and carried out in accordance with the regulatory requirements. While a long time, the verification of compliance was kept by the conduction of large scale monitoring programs around all the authorized installations. The IRD decided to reformulate its performance behavior, starting another kind of control program, due to the number increase of nuclear installations and the diversity of activities conducted by the operators. This program, so-called Monitoring Control Program (PCM) is a regulatory activity developed by the Environmental Impact Assessment Service (SEAIA) of IRD and has the aim of check the effectiveness of authorized self-control. Actually the regulatory control of environmental radiological integrity around the authorized nuclear installation essentially depends on the effectiveness of regulatory inspections fulfilled by the SEAIA/IRD. Due to the implementation of modern practices of management in the IRD, specially the quality management system on regulatory inspection activities, emerged the need of unify these actions. It was also necessary to establish standard procedures required for inspection conduction. This work proposes one methodology for the inspections of environmental radiological control suitable to assure the compliance and effectiveness of environmental and effluent monitoring programs conducted by the operator, through the systematic verification of compliance and data quality assessment. The proposed methodology seeks to attend the appeals for high control standards of environment protection and public health. Here, we presented as products of this work: The inspection handbook and checklists for inspections; one framework for sampling, handling, recording and reporting of

  1. Improved plant availability by advanced condition based inspections

    International Nuclear Information System (INIS)

    programme together with improved monitoring of operation parameters during operation has resulted in dramatic inspection interval extension. This attractive method for inspection interval extension has been applied at several Dutch power plants

  2. Results of calendar year 1995 Well Inspection and Maintenance Program Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    This document is a compendium of results of the 1995 Monitor Well Inspection and Maintenance Program at the US Department of Energy's Oak Ridge Y-12 Plant. This report documents the work relating to well inspections and maintenance requests. Inspections are implemented in order to better assess the condition and maintenance needs of wells that are actively being monitored. Currently this approach calls for inspecting all wells on a routine (annual or triennial) basis which are: (1) in an active sampling program; (2) included in a hydrologic study; or (3) not in service, but not scheduled for plugging and abandonment. Routine inspections help to ensure that representative groundwater samples and hydrologic data are being collected, and contribute to the effective longevity of each well. This report formally presents well inspection and maintenance activities that were conducted at the Y-12 Plant from August through December 1995

  3. Results of calendar year 1995 Well Inspection and Maintenance Program Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    McMaster, B.W. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Civil Engineering

    1996-07-01

    This document is a compendium of results of the 1995 Monitor Well Inspection and Maintenance Program at the US Department of Energy`s Oak Ridge Y-12 Plant. This report documents the work relating to well inspections and maintenance requests. Inspections are implemented in order to better assess the condition and maintenance needs of wells that are actively being monitored. Currently this approach calls for inspecting all wells on a routine (annual or triennial) basis which are: (1) in an active sampling program; (2) included in a hydrologic study; or (3) not in service, but not scheduled for plugging and abandonment. Routine inspections help to ensure that representative groundwater samples and hydrologic data are being collected, and contribute to the effective longevity of each well. This report formally presents well inspection and maintenance activities that were conducted at the Y-12 Plant from August through December 1995.

  4. Timeline Iraq: Challenges and lessons learned from nuclear inspections

    International Nuclear Information System (INIS)

    Under a dramatic and far-reaching global spotlight, the International Atomic Energy Agency's experience in Iraq reached a turning point in March 2003. Its nuclear inspection team - together with teams of the United Nations Monitoring, Verification and Inspection Commission (UNMOVIC) and the rest of the UN organisations operating in Iraq - had to withdraw ahead of announced military operations. The diplomatic route to disarming Iraq had reached an impasse. Today, international inspection teams tracking weapons of mass destruction (WMD) programmes in Iraq work in the wings, ready to resume operations in Iraq at the UN Security Council's call. The mandate of international inspection stands, with the IAEA's Iraq Nuclear Verification Office (INVO) in Vienna in charge of the nuclear file. The IAEA's nuclear inspection and verification experience in Iraq stretches over a span of three decades, addressing activities from the mine to the weapon. Agency inspectors led the discovery and dismantlement of Iraq's secret nuclear weapons programme in the 1990s, and after the 1990s round of inspections had stopped, they had found no evidence, up to March 2003, that the programme had been revived since 1998. Since the first Iraq inspections under Security Council mandate in early 1991, the road of nuclear verification in Iraq has proved to be long and hard, and valuable lessons were learned that have benefited the international community and strengthened the IAEA inspectorate. This article highlights the IAEA's extensive experience in Iraq, the main challenges, and selected key lessons drawn from them

  5. Safeguards management inspection procedures

    Energy Technology Data Exchange (ETDEWEB)

    Barth, M.J.; Dunn, D.R.

    1984-08-01

    The objective of this inspection module is to independently assess the contributions of licensee management to overall safeguards systems performance. The inspector accomplishes this objective by comparing the licensee's safeguards management to both the 10 CFR, parts 70 and 73, requirements and to generally accepted management practices. The vehicle by which this comparison is to be made consists of assessment questions and key issues which point the inspector to areas of primary concern to the NRC and which raise additional issues for the purpose of exposing management ineffectiveness. Further insight into management effectiveness is obtained through those assessment questions specifically directed toward the licensee's safeguards system performance. If the quality of the safeguards is poor, then the inspector should strongly suspect that management's role is ineffective and should attempt to determine management's influence (or lack thereof) on the underlying safeguards deficiencies. (The converse is not necessarily true, however.) The assessment questions in essence provide an opportunity for the inspector to identify, to single out, and to probe further, questionable management practices. Specific issues, circumstances, and concerns which point to questionable or inappropriate practices should be explicitly identified and referenced against the CFR and the assessment questions. The inspection report should also explain why the inspector feels certain management practices are poor, counter to the CFR, and/or point to ineffecive management. Concurrent with documenting the inspection results, the inspector should provide recommendations for alleviating observed management practices that are detrimental to effective safeguards. The recommendations could include: specific changes in the practices of the licensee, followup procedures on the part of NRC, and proposed license changes.

  6. Laser Safety Inspection Criteria

    International Nuclear Information System (INIS)

    A responsibility of the Laser Safety Officer (LSO) is to perform laser audits. The American National Standard Z136.1 Safe Use of Lasers references this requirement through several sections. One such reference is Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''. The composition, frequency and rigor of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms It is common for audit findings from one inspector or inspection to the next to vary even when reviewing the same material. How often has one heard a comment, ''well this area has been inspected several times over the years and no one ever said this or that was a problem before''. A great number of audit items, and therefore findings, are subjective because they are based on the experience and interest of the auditor to particular items on the checklist. Beam block usage, to one set of eyes might be completely adequate, while to another, inadequate. In order to provide consistency, the Laser Safety Office of the National Ignition Facility Directorate has established criteria for a number of items found on the typical laser safety audit form. The criteria are distributed to laser users. It serves two broad purposes; first, it gives the user an expectation of what will be reviewed by an auditor. Second, it is an opportunity to explain audit items to the laser user and thus the reasons for some of these items, such as labelling of beam blocks

  7. Safeguards management inspection procedures

    International Nuclear Information System (INIS)

    The objective of this inspection module is to independently assess the contributions of licensee management to overall safeguards systems performance. The inspector accomplishes this objective by comparing the licensee's safeguards management to both the 10 CFR, parts 70 and 73, requirements and to generally accepted management practices. The vehicle by which this comparison is to be made consists of assessment questions and key issues which point the inspector to areas of primary concern to the NRC and which raise additional issues for the purpose of exposing management ineffectiveness. Further insight into management effectiveness is obtained through those assessment questions specifically directed toward the licensee's safeguards system performance. If the quality of the safeguards is poor, then the inspector should strongly suspect that management's role is ineffective and should attempt to determine management's influence (or lack thereof) on the underlying safeguards deficiencies. (The converse is not necessarily true, however.) The assessment questions in essence provide an opportunity for the inspector to identify, to single out, and to probe further, questionable management practices. Specific issues, circumstances, and concerns which point to questionable or inappropriate practices should be explicitly identified and referenced against the CFR and the assessment questions. The inspection report should also explain why the inspector feels certain management practices are poor, counter to the CFR, and/or point to ineffecive management. Concurrent with documenting the inspection results, the inspector should provide recommendations for alleviating observed management practices that are detrimental to effective safeguards. The recommendations could include: specific changes in the practices of the licensee, followup procedures on the part of NRC, and proposed license changes

  8. Comparative study of Palito inspection and MFL Inspection

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Anne A. de; Miranda, Ivan Vicente Janvrot; Silva, Jose Augusto Pereira da [Pipeway Engenharia, Rio de Janeiro, RJ (Brazil); Guimaraes, Frederico S.; Magalhaes, Joao Alfredo P. [Minds at Work, Rio de Janeiro, RJ (Brazil); Sabino, Joao Marcos [Petroleo Brasileiro S.A. (PETROBRAS/UN-RN/CE), Natal, RN (Brazil). Unidade de Negocios Rio Grande do Norte e Ceara

    2009-07-01

    A 16 inches oil pipeline was surveyed with MFL and Palito pig in 2007. The MFL inspection was performed by Pipeway Engenharia while Palito inspection was performed by PETROBRAS. A comparison between the results of these two ILI inspections has been made to validate Palito Pig and to assess main characteristics and differences between the two techniques. The purpose of this paper is to detail the methodology applied to perform the comparison and to present a comparative study of results registered in the MFL and Palito inspections by Pipeway Engenharia, PETROBRAS/CENPES and CPTI/PUC-Rio. (author)

  9. Realization by inspection

    OpenAIRE

    Rosenthal, J.; Schumacher, Hans

    1997-01-01

    We investigate which first-order representations can be obtained from high-order representations of linear systems “by inspection”, that is, just by rearrangement of the data. Under quite weak conditions it is possible to obtain minimal realizations in the so-called pencil form; under stronger conditions one can obtain minimal realizations in standard state-space form by inspection. The development is based on a reformulation of the realization problem as a problem of finding a complete set o...

  10. Tonopah Test Range Post-Closure Inspection Annual Report, Tonopah Test Range, Nevada, Calendar Year 2002

    Energy Technology Data Exchange (ETDEWEB)

    R. B. Jackson

    2003-08-01

    This Post-Closure Inspection Annual Report provides documentation of the semiannual inspections conducted at the following Corrective Action Units (CAU)s: CAU 400: Bomblet Pit and Five Points Landfill; CAU 404: Roller Coaster Lagoons and Trench; CAU 407: Roller Coaster RadSafe Area; CAU 424: Area 3 Landfill Complexes; CAU 426: Cactus Spring Waste Trenches; CAU 427: Septic Waste Systems 2, 6; and CAU 453: Area 9 UXO Landfill, all located at the Tonopah Test Range, Nevada. Post-closure inspections are not required at CAU 400 but are conducted to monitor vegetation and fencing at the site. Site inspections were conducted in May and November 2002. All site inspections were made after Nevada Division of Environmental Protection (NDEP) approval of the appropriate Closure Report (CR), excluding CAU 400 which did not require a CR, and were conducted in accordance with the Post-Closure Inspection Plans in the NDEP-approved CRs. Post-closure inspections conducted during 2002 identified several areas requiring maintenance/repairs. Maintenance work and proposed additional monitoring are included in the appropriate section for each CAU. This report includes copies of the Post-Closure Inspection Plans, Post-Closure Inspection Checklists, copies of the field notes, photographs, and the Post-Closure Vegetative Monitoring Report. The Post-Closure Inspection Plan for each CAU is located in Attachment A. Post-Closure Inspection Checklists are in Attachment B. Copies of the field notes from each inspection are included in Attachment C. Attachment D consists of the photographic logs and photographs of the sites. The post-closure vegetative monitoring report for calendar year 2002 is included in Attachment E.

  11. INSPECTION OF CNC MADE PARTS

    OpenAIRE

    Prof. Yogesh R. Falak*; Rahul Patil; Kalpesh Bhagat,

    2015-01-01

    Inspection is an important process of manufacturing system. It is means of rejecting error parts and assuring good quality parts. The advantages of technological innovation in inspection equipment helped to overcome the problems associated with traditional approaches. Such means that used of labour intensive method increase in total manufacturing time and production cost. Advanced sensor and inspection technologies, interfaced with computer based systems to automate the operations...

  12. Inspections - a cost effective approach

    International Nuclear Information System (INIS)

    This paper describes a cost effective approach for inspections of Computerized Nuclear Materials Control and Accounting Systems (CNMCAS). Highlighted is the capability to conduct an inspection program via portable telephone terminals from off-site locations. The program can be applied to various materials management functions including materials control, quality assurance, and materials accounting. The system is designed to facilitate inspections by both external and internal groups

  13. Waste inspection tomography (WIT)

    Energy Technology Data Exchange (ETDEWEB)

    Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

    1995-10-01

    Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU.

  14. Waste inspection tomography (WIT)

    International Nuclear Information System (INIS)

    The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented

  15. Ultrasonic wave inspection device

    International Nuclear Information System (INIS)

    The device of the present invention inspects incore structural components by visualizing them by scanning an ultrasonic transducer in an opaque liquid metal sodium in a pressure vessel of an FBR type reactor. Namely, a piezoelectric vibrator for transmitting/receiving ultrasonic waves is formed into a protruded shape. A portion at the center of the protruded piezoelectric vibrator is coaxially separated. Upon transmitting ultrasonic waves, a large opening of the entire piezoelectric vibrator is used. A small opening at the center of the piezoelectric vibrator is used upon receiving ultrasonic waves. With such a constitution, an object to be inspected is visualized based on the waveform of the received ultrasonic wave signals defining the center of a curvature of the protruded piezoelectric vibrator as a position of transmitting ultrasonic waves and defining the center of the opening at the center of the piezoelectric vibrator as a position of receiving ultrasonic waves. As a result, the energy of the ultrasonic waves can be enhanced to improve sensitivity upon transmitting ultrasonic waves. Since the distance between an optional position of the receiving surface and the reflecting surface of the object is minimized upon receiving ultrasonic waves, there is no distortion in the waveforms of the received signals thereby enabling to obtain images at high accuracy. (I.S.)

  16. Smart pigging - a contribution to the monitoring of the anti-corrosion protection systems on pig-inspectable high-pressure gas transmission pipelines; Intelligente Molchung - ein Beitrag zur Ueberwachung des Korrosionsschutzes molchbarer Gashochdruckleitungen

    Energy Technology Data Exchange (ETDEWEB)

    Ahlers, M.; Schoeneich, H.G. [Ruhrgas AG, Essen (Germany). Kompetenz-Center Korrosionsschutz

    2000-07-01

    High-pressure gas transmission pipelines installed underground are exposed to the risk of external corrosion. The application of a sheathing (passive protection) and, since the 1950s, the installation of a cathodic anti-corrosion protection system, provide pipelines with effective protection against this danger. In the past, the effectiveness of cathodic anti-corrosion protection systems was verified by means of intensive measuring and re-measuring cycles. It became apparent that points of damage to the sheathing were protected in the majority of cases against corrosion by the cathodic anti-corrosion protection system. There are, however, particular design circumstances and ambient conditions which can make this anti-corrosion protection concept either partially or completely ineffective. The use of smart pigs for inspection of pig-inspectable gas transmission pipelines makes it possible to detect and eliminate these weak points. (orig.) [German] Gashochdruckleitungen, die im Erdboden verlegt werden, unterliegen einer Gefaehrdung durch Aussenkorrosion. Durch eine Umhuellung (passiver Schutz) und seit den 50er Jahren durch die Einrichtung des kathodischen Korrosionsschutzes (aktiver Schutz) sind die Leitungen gegen diese Gefaehrdung wirkungsvoll geschuetzt. In der Vergangenheit wurde die Ueberpruefung der Wirksamkeit des kathodischen Korrosionsschutzes durch Intensivmessungen und Nachmessungen sichergestellt. Dabei zeigte sich, dass in der ueberwiegenden Zahl Umhuellungsbeschaedigungen durch den kathodischen Korrosionsschutz gegen Korrosion geschuetzt sind. Es gibt jedoch besondere konstruktive oder Umgebungsbedingungen, die dieses Korrosionsschuzkonzept teilweise oder vollstaendig unwirksam werden lassen. Mit dem Einsatz von intelligenten Molchen zur Inspektion molchbarer Gastransportleitungen koennen diese Schwachstellen erkannt und beseitigt werden. (orig.)

  17. Inspection system performance test procedure

    International Nuclear Information System (INIS)

    This procedure establishes requirements to administer a performance demonstration test. The test is to demonstrate that the double-shell tank inspection system (DSTIS) supplied by the contractor performs in accordance with the WHC-S-4108, Double-Shell Tank Ultrasonic Inspection Performance Specification, Rev. 2-A, January, 1995. The inspection system is intended to provide ultrasonic (UT) and visual data to determine integrity of the Westinghouse Hanford Company (WHC) site underground waste tanks. The robotic inspection system consists of the following major sub-systems (modules) and components: Mobile control center; Deployment module; Cable management assembly; Robot mechanism; Ultrasonic testing system; Visual testing system; Pneumatic system; Electrical system; and Control system

  18. Optimal allocation of inspection resources

    International Nuclear Information System (INIS)

    Allocation of inspection resources for international safeguards is considered as the problem of designing a complex system that is composed of individual inspection activities and that has the objective of detecting material loss. Optimization theory is applied in selecting those inspection activities that maximize a system performance measure within resource constraints. The method is applicable to a global allocation problem in which inspection resources are distributed throughout a hierarchy consisting of multiple countries, multiple facilities within each country, and multiple activities within each facility. 9 references

  19. Development of inspection safety evaluation technology

    International Nuclear Information System (INIS)

    The purpose of this project is to protection nation inspector's over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector's over exposure from radiation at domestic nuclear facilities. Management of inspector's exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs

  20. Laser Safety Inspection Criteria

    International Nuclear Information System (INIS)

    A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an

  1. Labor inspection in Brazil

    Directory of Open Access Journals (Sweden)

    Adalberto Cardoso

    2006-01-01

    Full Text Available One aspect the literature overlooks on the effects of labor regulation of labor market efficiency is the degree of the legislation's effectiveness, i.e., its actual enforcement in daily work relations. Even the more sophisticated econometric studies (which take into account the effects of interaction between labor market regulatory institutions in explaining its dynamics leave this central issue aside, namely enforcement versus non-enforcement of the law. Keeping this issue in mind, we seek to answer the following question in this article: given that the effectiveness of labor legislation depends on the interaction between the overall sanctions and the probability of the employer getting caught breaking the law, and given that the law's effectiveness is a decisive aspect for the real measurement of a country's labor costs, to what extent is the Brazilian labor inspection system designed to meet its objective, namely, to enforce the law?

  2. Automated visual inspection of textile

    DEFF Research Database (Denmark)

    Jensen, Rune Fisker; Carstensen, Jens Michael

    A method for automated inspection of two types of textile is presented. The goal of the inspection is to determine defects in the textile. A prototype is constructed for simulating the textile production line. At the prototype the images of the textile are acquired by a high speed line scan camera...

  3. Inspection of disposal canisters components

    International Nuclear Information System (INIS)

    This report presents the inspection techniques of disposal canister components. Manufacturing methods and a description of the defects related to different manufacturing methods are described briefly. The defect types form a basis for the design of non-destructive testing because the defect types, which occur in the inspected components, affect to choice of inspection methods. The canister components are to nodular cast iron insert, steel lid, lid screw, metal gasket, copper tube with integrated or separate bottom, and copper lid. The inspection of copper material is challenging due to the anisotropic properties of the material and local changes in the grain size of the copper material. The cast iron insert has some acoustical material property variation (attenuation, velocity changes, scattering properties), which make the ultrasonic inspection demanding from calibration point of view. Mainly three different methods are used for inspection. Ultrasonic testing technique is used for inspection of volume, eddy current technique, for copper components only, and visual testing technique are used for inspection of the surface and near surface area

  4. Planning and performance of inspections

    International Nuclear Information System (INIS)

    Inspections in power plants are decisive factors for profitable and safe power production. Inspection schedulling needs to consider output demand, fuel application, manufacturers' recommendations and, above all, operational records of the state of the plant. Inspection schedulling is aimed at finding an optimum time-to-cost ratio for a defined scope of inspection. A large utility with a power plant pool featuring nuclear, black coal, brown coal, gas and hydro electric plants makes great and varied demands on inspection schedulling and implementation which the author exemplifies by PreussenElektra with its installed capacity of ca. 12,000 MW distributed among 7 nuclear power plants, 20 coal and gas units, 10 pump storage units and 40 run-of-river turbines. (orig./GL)

  5. Reliable NDT data risk based inspection for offshore structures

    Energy Technology Data Exchange (ETDEWEB)

    Rouhan, A. [Bureau Veritas, Marine Div., Research Dept., Courbevoie (France)

    2002-07-01

    The monitoring of existing structures is more and more based on probabilistic approaches suck as risk based inspection (RBI). In order to minimise risks and costs in monitoring, reliable inspection data are of great importance, all the more inspection, maintenance and repair (IMR) campaigns are carried out at a low frequency. This is the case for offshore structures, with expensive non-destructive underwater inspections. This kind of harsh environment leads to lower in-situ performances than those obtained in laboratory. PoD data are often used in current RBI approaches. However, false alarms are not considered in spite of some results of the ICON project (InterCalibration of Offshore NDT), showing a significant number of false indications. In this paper, some data on underwater inspections on tubular nodes are presented. It is shown how ROC curves, Pod and PFI data where obtained within the ICON project. From a structural point of view, this paper then underlines the role of false alarms in a RBI process, using a cost function and both the probability of detection and the probability of false alarm. The basic policy ''repair when crack is detected'' and ''do nothing when no crack is detected'' is shown to be not optimal, underlining the necessity to use false alarms. (orig.)

  6. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from July 1989 through September 1989

  7. Licensee contractor and Vendor Inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1992 through December 1992

  8. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from January 1991 through March 1991

  9. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1989 through December 1989

  10. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from April through June 1993

  11. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from January 1993 through March 1993

  12. Licensee contractor and Vendor Inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from January through March 1992

  13. Licensee Contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from October through December 1991

  14. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from January 1990 through March 1990

  15. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from April 1990 through June 1990

  16. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from July 1992 through September 1992

  17. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period from October 1990 through December 1990

  18. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from April 1991 through June 1991

  19. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organization during the period from July 1991 through September 1991

  20. An intelligent inspection and survey robot. Volume 1

    International Nuclear Information System (INIS)

    ARIES number-sign 1 (Autonomous Robotic Inspection Experimental System), has been developed for the Department of Energy to survey and inspect drums containing low-level radioactive waste stored in warehouses at DOE facilities. The drums are typically stacked four high and arranged in rows with three-foot aisle widths. The robot will navigate through the aisles and perform an inspection operation, typically performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. A new version of the Cybermotion series of mobile robots is the base mobile vehicle for ARIES. The new Model K3A consists of an improved and enhanced mobile platform and a new turret that will permit turning around in a three-foot aisle. Advanced sonar and lidar systems were added to improve navigation in the narrow drum aisles. Onboard computer enhancements include a VMEbus computer system running the VxWorks real-time operating system. A graphical offboard supervisory UNIX workstation is used for high-level planning, control, monitoring, and reporting. A camera positioning system (CPS) includes primitive instructions for the robot to use in referencing and positioning the payload. The CPS retracts to a more compact position when traveling in the open warehouse. During inspection, the CPS extends up to deploy inspection packages at different heights on the four-drum stacks of 55-, 85-, and 110-gallon drums. The vision inspection module performs a visual inspection of the waste drums. This system will locate and identify each drum, locate any unique visual features, characterize relevant surface features of interest and update a data-base containing the inspection data

  1. An intelligent inspection and survey robot. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-15

    ARIES {number_sign}1 (Autonomous Robotic Inspection Experimental System), has been developed for the Department of Energy to survey and inspect drums containing low-level radioactive waste stored in warehouses at DOE facilities. The drums are typically stacked four high and arranged in rows with three-foot aisle widths. The robot will navigate through the aisles and perform an inspection operation, typically performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. A new version of the Cybermotion series of mobile robots is the base mobile vehicle for ARIES. The new Model K3A consists of an improved and enhanced mobile platform and a new turret that will permit turning around in a three-foot aisle. Advanced sonar and lidar systems were added to improve navigation in the narrow drum aisles. Onboard computer enhancements include a VMEbus computer system running the VxWorks real-time operating system. A graphical offboard supervisory UNIX workstation is used for high-level planning, control, monitoring, and reporting. A camera positioning system (CPS) includes primitive instructions for the robot to use in referencing and positioning the payload. The CPS retracts to a more compact position when traveling in the open warehouse. During inspection, the CPS extends up to deploy inspection packages at different heights on the four-drum stacks of 55-, 85-, and 110-gallon drums. The vision inspection module performs a visual inspection of the waste drums. This system will locate and identify each drum, locate any unique visual features, characterize relevant surface features of interest and update a data-base containing the inspection data.

  2. Visual inspection for CTBT verification

    Energy Technology Data Exchange (ETDEWEB)

    Hawkins, W.; Wohletz, K.

    1997-03-01

    On-site visual inspection will play an essential role in future Comprehensive Test Ban Treaty (CTBT) verification. Although seismic and remote sensing techniques are the best understood and most developed methods for detection of evasive testing of nuclear weapons, visual inspection can greatly augment the certainty and detail of understanding provided by these more traditional methods. Not only can visual inspection offer ``ground truth`` in cases of suspected nuclear testing, but it also can provide accurate source location and testing media properties necessary for detailed analysis of seismic records. For testing in violation of the CTBT, an offending party may attempt to conceal the test, which most likely will be achieved by underground burial. While such concealment may not prevent seismic detection, evidence of test deployment, location, and yield can be disguised. In this light, if a suspicious event is detected by seismic or other remote methods, visual inspection of the event area is necessary to document any evidence that might support a claim of nuclear testing and provide data needed to further interpret seismic records and guide further investigations. However, the methods for visual inspection are not widely known nor appreciated, and experience is presently limited. Visual inspection can be achieved by simple, non-intrusive means, primarily geological in nature, and it is the purpose of this report to describe the considerations, procedures, and equipment required to field such an inspection.

  3. From PISC to risk informed inspection

    International Nuclear Information System (INIS)

    In this paper the correlation between inspection effectiveness, inspection qualification and risk informed inspection will be treated in view of harmonisation of inspection of nuclear plant components. Through the different phases of the PISC programme the necessity has been demonstrated to show the effectiveness of the inspection through a formal process of qualification in order to ensure that a certain level of effectiveness has been reached. Inspection qualification is indeed the way to quantify the capability level of inspection techniques used. The targets to be met by the inspection is information which should be obtained from risk based analyses. (author)

  4. Verification of Remote Inspection Techniques for Reactor Internal Structures of Liquid Metal Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Young Sang; Lee, Jae Han

    2007-02-15

    The reactor internal structures and components of a liquid metal reactor (LMR) are submerged in hot sodium of reactor vessel. The division 3 of ASME code section XI specifies the visual inspection as major in-service inspection (ISI) methods of reactor internal structures and components. Reactor internals of LMR can not be visually examined due to opaque liquid sodium. The under-sodium viewing techniques using an ultrasonic wave should be applied for the visual inspection of reactor internals. Recently, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium inspection. In this study, visualization technique, ranging technique and monitoring technique have been suggested for the remote inspection of reactor internals by using the waveguide sensor. The feasibility of these remote inspection techniques using ultrasonic waveguide sensor has been evaluated by an experimental verification.

  5. Review of current practices and requirements for the inspection of prestressed concrete pressure vessels

    International Nuclear Information System (INIS)

    Code requirements for pre- and in-service inspection of prestressed concrete pressure vessels as utilized in gas-cooled reactors are reviewed and compared with practices and experiences during construction, commissioning, and operation of such reactors. The pre-service inspection relies heavily on embedded instrumentation for measurements of stresses, temperatures, and displacements. The same instrumentation is later used for in-service surveillance, which additionally includes visual examination of exposed surfaces, monitoring of tendon conditions, and measurement of tendon loads. Improvement of present monitoring instrumentation and/or techniques, rather than development of new in-service inspection methods, is recommended

  6. Final inspection of photomask blanks

    Science.gov (United States)

    Schubert, Fredi; Sauerbrei, Hartmut; Aschke, Lutz; Knapp, Konrad

    2001-04-01

    In order to increase the quality in manufacturing of future photon mask generations Schott Lithotec is brought in a brand new, much increased automatic laser inspection system into a new manufacturing line of photo mask blanks. It is in a position to detect additionally to the standard defect types further defect types like dim- and bright-chrome defects. The resolution of the system is less than 100 nm. With a quickly inspecting time per blank of less than three minutes and for the first time in the world used automatic SMIF-pod-handling this is a tool for the 100 percent final inspection in the manufacturing of photo mask blanks.

  7. Non-destructive inservice inspections

    International Nuclear Information System (INIS)

    In order to assess the possible damages occurring in the components and structures of operating nuclear power plants during service the main components and structures are periodically inspected by non-destructive testing techniques. The reliability of non-destructive testing techniques applied in these inservice inspections is of major importance because the decisions concerning the needs for repair of components are mainly based on the results of inspections. One of the targets of this research program has been to improve the reliability of non-destructive testing. This has been addressed in the sub-projects which are briefly summarised here. (author)

  8. Inspections are the key. Essay, published in the Washington Post, Page A 25. 21 October 2002

    International Nuclear Information System (INIS)

    Inspections by an impartial, credible third party have been a cornerstone of international nuclear arms control agreements for decades. Where the intent exists to develop a clandestine nuclear weapons program, inspections serve effectively as a means of both detection and deterrence. From 1991 through 1998, the International Atomic Energy Agency, empowered by the U.N. Security Council with broad rights of inspection, succeeded in thwarting Iraq's efforts to develop nuclear weapons - the most lethal weapons of mass destruction. The Iraq's nuclear program was neutralized. The problem arose in 1998, when all inspections were brought to a halt, with a military strike imminent. After four years, the door to inspections has finally reopened, and the advantage should be taken of that opportunity. The success of inspections in Iraq -- in eliminating not only nuclear weapons, but also biological and chemical ones - will depend on five interrelated prerequisites: full and explicit authority for inspection; ready access to all sources of information; unified and robust support from the UN Security Council; preservation of integrity and objectivity in the inspection process; active cooperation by Iraq. Concurrent with the inspections in Iraq, strong action should be taken worldwide to ensure the physical protection of nuclear material, with effective control of weapons-relevant exports and vigilant border monitoring to detect any attempts at illicit smuggling. Regardless of how events unfold in the near future, inspections will be the key, over the long haul, to ensuring that clandestine efforts to develop nuclear weapons in Iraq or elsewhere are detected and thwarted

  9. Simulation examples of ultrasonic inspection

    International Nuclear Information System (INIS)

    The paper gives examples of application of two very different computer programs that are used to simulate and model ultrasonic inspection. The real propagation path of the sound beam can be difficult to trace when the geometry is complex. Ray tracing simulation on a three dimensional model of the inspection geometry can be very useful and sometimes nearly a necessity to analyse the probe angles and scanning paths. The modelling of the sound pulse behaviour in the material and its interaction with geometric details and defects produces information about the signals that can occur during the inspection. Simulation examples show how information can be generated to support inspection design, data analyses and qualification. (orig.)

  10. Incore inspection and repairing device

    International Nuclear Information System (INIS)

    The present invention provides a device for inspecting and repairing the inside of a reactor container even if it is narrow, with no trouble by using a swimming-type operation robot. Namely, the device of the present invention conducts inspection and repairing operations for the inside of the reactor by introducing a swimming type operation robot into the reactor container. The swimming-type operation robot comprises a robot main body having a propeller, a balancer operably disposed to the robot main body and an inspection and repairing unit attached detachable to the balancer. In the device of the present invention, since the inspection and preparing unit is attached detachably to the swimming robot, a robot which transports tools is formed as a standard product. As a result, the production cost can be reduced, and the reliability of products can be improved. Appropriate operations can be conducted by using best tools. (I.S.)

  11. Multifamily Housing Physical Inspection Scores

    Data.gov (United States)

    Department of Housing and Urban Development — HUD's Real Estate Assessment Center conducts physical property inspections of properties that are owned, insured or subsidized by HUD, including public housing and...

  12. National Automated Conformity Inspection Process

    Data.gov (United States)

    Department of Transportation — The National Automated Conformity Inspection Process (NACIP) Application is intended to expedite the workflow process as it pertains to the FAA Form 81 0-10 Request...

  13. CIGAR - a remote inspection system

    International Nuclear Information System (INIS)

    CIGAR (Channel Inspection and Gauging Apparatus for Reactors) is an automated system that has been developed by Ontario Hydro, Canadian General Electric and AECL for the inspection of pressure tubes in CANDU reactors. It performs volumetric flaw detection, diameter and wall thickness measurement, sag profile measurement and spacer location determination. The inspection systems employed may have application in other situations and they well demonstrate the capabilities that exist in Canada for the development of sophisticated technology to solve complex problems. Part 1 of this paper discusses the requirements for the system and describes the CIGAR inspection, data acquisition and processing components that were developed by Ontario Hydro's Research Division. Part 2 describes the CIGAR delivery system that was developed by Canadian General Electric

  14. Sea bed mapping and inspection

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The conference has 24 presentations on the topics: Sea bed mapping, inspection, positioning, hydrography, marine archaeology, remote operation vehicles and computerized simulation technologies, oil field activities and plans, technological experiences and problems. (tk)

  15. Ultrasonic Inspection Of Thick Sections

    Science.gov (United States)

    Friant, C. L.; Djordjevic, B. B.; O'Keefe, C. V.; Ferrell, W.; Klutz, T.

    1993-01-01

    Ultrasonics used to inspect large, relatively thick vessels for hidden defects. Report based on experiments in through-the-thickness transmission of ultrasonic waves in both steel and filament-wound composite cases of solid-fuel rocket motors.

  16. Ultrasonic inspection of austenitic welds

    International Nuclear Information System (INIS)

    The metallurgical structure of austenitic welds is described and contrasted with that found in ferritic welds. It is shown that this structure imparts a marked elastic anisotropy in the ultrasonic propagation parameters. Measurements of variations in the apparent attenuation of sound and deviations in the beam direction are described. The measurements are interpreted in terms of the measured velocity anisotropy. Two applications of the fundamental work are described. In the first it is shown how, by using short pulse compression wave probes, and with major modification of the welding procedure, a stainless steel fillet weld in an AGR boiler can be inspected. In the second application, alternative designs of a transition butt weld have been compared for ease of ultrasonic inspection. The effects of two different welding processes on such an inspection are described. Finally, the paper examines the prospects for future development of inspection and defect-sizing techniques for austenitic welds. (author)

  17. Public Housing Physical Inspection Scores

    Data.gov (United States)

    Department of Housing and Urban Development — HUD's Real Estate Assessment Center conducts physical property inspections of properties that are owned, insured or subsidized by HUD, including public housing and...

  18. Virtual World Security Inspection

    Directory of Open Access Journals (Sweden)

    Nicholas Charles Patterson

    2012-06-01

    Full Text Available Virtual property theft is a serious problem that exists in virtual worlds. Legitimate users of these worlds invest considerable amounts of time, effort and real-world money into obtaining virtual property, but unfortunately, are becoming victims of theft in high numbers. It is reported that there are over 1 billion registered users of virtual worlds containing virtual property items worth an estimated US$50 billion dollars. The problem of virtual property theft is complex, involving many legal, social and technological issues. The software used to access virtual worlds is of great importance as they form the primary interface to these worlds and as such the primary interface to conduct virtual property theft. The security vulnerabilities of virtual world applications have not, to date, been examined. This study aims to use the process of software inspection to discover security vulnerabilities that may exist within virtual world software – vulnerabilities that enable virtual property theft to occur. Analyzing three well know virtual world applications World of Warcraft, Guild Wars and Entropia Universe, this research utilized security analysis tools and scenario testing with focus on authentication, trading, intruder detection and virtual property recovery. It was discovered that all three examples were susceptible to keylogging, mail and direct trade methods were the most likely method for transferring stolen items, intrusion detection is of critical concern to all VWEs tested, stolen items were unable to be recovered in all cases and lastly occurrences of theft were undetectable in all cases. The results gained in this study present the key problem areas which need to be addressed to improve security and reduce the occurrence of virtual property theft.

  19. Automation of painted slate inspection

    OpenAIRE

    Carew, Tim

    2002-01-01

    This thesis is concerned with the problem of how to detect visual defects on painted slates using an automated visual inspection system. The vision system that has been developed consists of two major components. The first component addresses issues such as the mechanical implementation and interfacing the inspection system with the optical and sensing equipment whereas the second component involves the development of an image processing algorithm able to identify the visual defects present o...

  20. Ultrasonic nondestructive tubing inspection system

    International Nuclear Information System (INIS)

    A system for measuring the extent of tube wall erosion in an inspection region of a heat exchanger tube of a nuclear steam generator, uses an ultrasonic means driven helically inside the eroded tube which may be filled with a fluid (e.g., water) to minimize ultrasonic wave attenuation. A control means cooperates with the ultrasonic means to produce a map of the tube wall thickness in an inspection region

  1. Ultrasonic inspection of inpile tubes

    International Nuclear Information System (INIS)

    The in-service inspection (ISI) of inpile tubes can be performed accurately and safely with a semiautomatic ultrasonic inspection system. The ultrasonic technique uses a set of multiple transducers to detect and size cracks, voids, and laminations radially and circumferentially. Welds are also inspected for defects. The system is designed to inspect stainless steel and Inconel tubes ranging from 53.8 mm (2.12 in.) to 101.6 mm (4 in.) inner diameter with wall thickness on the order of 5 mm. The inspection head contains seven transducers mounted in a surface-following device. Six angle-beam transducers generate shear waves in the tubes. Two of the six are oriented to detect circumferential cracks, and two detect axial cracks. Although each of these four transducers is used in the pulse-echo mode, they are oriented in aligned sets so pitch-catch operation is possible if desired. The remaining angle-beam transducers are angulated to detect flaws that are off axial or circumferential orientation. The seventh transducer is used for longitudinal inspection and detects and sizes laminar-type defects

  2. Risk based inspection programmes; Risikobaserte inspeksjonsprogrammer

    Energy Technology Data Exchange (ETDEWEB)

    Haugland, Haakon

    1998-07-01

    Risk based inspection is a method of selecting which parts or components of an offshore installation should be inspected and when if the resources available for inspection is to be fully exploited. By inspecting the components involving the highest risk, an optimum risk reduction is achieved. The risk level is a function of fault probability and fault consequence.

  3. 49 CFR Appendix A to Part 230 - Inspection Requirements

    Science.gov (United States)

    2010-10-01

    .... Inspection of brake cylinders for piston travel. 11. Inspection of foundation brake gear. 12. Inspection of... crossheads and guides. 16. Inspection of piston rods and fasteners. 17. Inspection of main, side, and...

  4. ROBOTIC TANK INSPECTION END EFFECTOR

    Energy Technology Data Exchange (ETDEWEB)

    Rachel Landry

    1999-10-01

    The objective of this contract between Oceaneering Space Systems (OSS) and the Department of Energy (DOE) was to provide a tool for the DOE to inspect the inside tank walls of underground radioactive waste storage tanks in their tank farms. Some of these tanks are suspected to have leaks, but the harsh nature of the environment within the tanks precludes human inspection of tank walls. As a result of these conditions only a few inspection methods can fulfill this task. Of the methods available, OSS chose to pursue Alternating Current Field Measurement (ACFM), because it does not require clean surfaces for inspection, nor any contact with the Surface being inspected, and introduces no extra by-products in the inspection process (no coupling fluids or residues are left behind). The tool produced by OSS is the Robotic Tank Inspection End Effector (RTIEE), which is initially deployed on the tip of the Light Duty Utility Arm (LDUA). The RTEE combines ACFM with a color video camera for both electromagnetic and visual inspection The complete package consists of an end effector, its corresponding electronics and software, and a user's manual to guide the operator through an inspection. The system has both coarse and fine inspection modes and allows the user to catalog defects and suspected areas of leakage in a database for further examination, which may lead to emptying the tank for repair, decommissioning, etc.. The following is an updated report to OSS document OSS-21100-7002, which was submitted in 1995. During the course of the contract, two related subtasks arose, the Wall and Coating Thickness Sensor and the Vacuum Scarifying and Sampling Tool Assembly. The first of these subtasks was intended to evaluate the corrosion and wall thinning of 55-gallon steel drums. The second was retrieved and characterized the waste material trapped inside the annulus region of the underground tanks on the DOE's tank farms. While these subtasks were derived from the original

  5. ROBOTIC TANK INSPECTION END EFFECTOR

    International Nuclear Information System (INIS)

    The objective of this contract between Oceaneering Space Systems (OSS) and the Department of Energy (DOE) was to provide a tool for the DOE to inspect the inside tank walls of underground radioactive waste storage tanks in their tank farms. Some of these tanks are suspected to have leaks, but the harsh nature of the environment within the tanks precludes human inspection of tank walls. As a result of these conditions only a few inspection methods can fulfill this task. Of the methods available, OSS chose to pursue Alternating Current Field Measurement (ACFM), because it does not require clean surfaces for inspection, nor any contact with the Surface being inspected, and introduces no extra by-products in the inspection process (no coupling fluids or residues are left behind). The tool produced by OSS is the Robotic Tank Inspection End Effector (RTIEE), which is initially deployed on the tip of the Light Duty Utility Arm (LDUA). The RTEE combines ACFM with a color video camera for both electromagnetic and visual inspection The complete package consists of an end effector, its corresponding electronics and software, and a user's manual to guide the operator through an inspection. The system has both coarse and fine inspection modes and allows the user to catalog defects and suspected areas of leakage in a database for further examination, which may lead to emptying the tank for repair, decommissioning, etc.. The following is an updated report to OSS document OSS-21100-7002, which was submitted in 1995. During the course of the contract, two related sub-tasks arose, the Wall and Coating Thickness Sensor and the Vacuum Scarifying and Sampling Tool Assembly. The first of these sub-tasks was intended to evaluate the corrosion and wall thinning of 55-gallon steel drums. The second was retrieved and characterized the waste material trapped inside the annulus region of the underground tanks on the DOE's tank farms. While these sub-tasks were derived from the original intent

  6. OSE inspection of protection program operations field perspective of inspections

    International Nuclear Information System (INIS)

    Protection Program Operations includes three functional areas: Physical Protection Systems, Protective Forces, and System Performance Testing. The Office of Security Evaluations (OSE) inspects field offices in these areas by evaluating programs relative to Standards and Criteria and by performing a variety of exercises and other types of tests to assure protective systems are effective and maintained at a proper level to meet the defined threat. Their perception of the OSE inspections has been positive. The approach taken by ID, with key areas/activities emphasized, during each phase of the field inspection process is described in this report. The most important areas for field offices to concentrate are: inspection preparations through self-evaluation, improving communications, assigning knowledgeable trusted agents, increasing awareness of facility procedures and operations, and assuring daily validations of inspected areas. Emphasis is placed on striving for a balance in reporting both positive and negative findings, and for consistency between ratings and the importance of report findings. OSE efforts to develop improved rating methodologies are encouraged

  7. Restaurant Inspection Scores and Foodborne Disease

    OpenAIRE

    Jones, Timothy F.; Pavlin, Boris I; LaFleur, Bonnie J.; Ingram, L. Amanda; Schaffner, William

    2004-01-01

    Restaurants in the United States are regularly inspected by health departments, but few data exist regarding the effect of restaurant inspections on food safety. We examined statewide inspection records from January 1993 through April 2000. Data were available from 167,574 restaurant inspections. From 1993 to 2000, mean scores rose steadily from 80.2 to 83.8. Mean inspection scores of individual inspectors were 69–92. None of the 12 most commonly cited violations were critical food safety haz...

  8. Examination of the association between announced inspections and inspection scores.

    Science.gov (United States)

    Waters, A Blake; VanDerslice, James; Porucznik, Christina A; Kim, Jaewhan; DeLegge, Royal; Durrant, Lynne

    2013-09-01

    In 2010 the Salt Lake Valley Health Department conducted a pilot of an announced inspection program utilizing a randomized assignment of restaurants to an intervention group with announced inspections and a control group that remained on the usual schedule of unannounced inspections. After adjusting for food type, visible kitchen, outside quality assurance, season, and standardized inspector, significant reductions were found in the odds ratios of personal hygiene (adjusted odds ratios [aOR] = 0.11, p = .00) and equipment cleanliness (aOR = 0.19, p = .00) violations. In the models for the control group, none of the odds ratios were statistically different from one, indicating no change in the postintervention time period as compared to the preintervention period. PMID:24073484

  9. Automated optics inspection analysis for NIF

    International Nuclear Information System (INIS)

    The National Ignition Facility (NIF) is a high-energy laser facility comprised of 192 beamlines that house thousands of optics. These optics guide, amplify and tightly focus light onto a tiny target for fusion ignition research and high energy density physics experiments. The condition of these optics is key to the economic, efficient and maximally energetic performance of the laser. Our goal, and novel achievement, is to find on the optics any imperfections while they are tens of microns in size, track them through time to see if they grow and if so, remove the optic and repair the single site so the entire optic can then be re-installed for further use on the laser. This paper gives an overview of the image analysis used for detecting, measuring, and tracking sites of interest on an optic while it is installed on the beamline via in situ inspection and after it has been removed for maintenance. In this way, the condition of each optic is monitored throughout the optic's lifetime. This overview paper will summarize key algorithms and technical developments for custom image analysis and processing and highlight recent improvements. (Associated papers will include more details on these issues.) We will also discuss the use of OI Analysis for daily operation of the NIF laser and its extension to inspection of NIF targets.

  10. Independent validation of ultrasonic inspection

    International Nuclear Information System (INIS)

    As a part of its inspection strategy for the Sizewell-B PWR station, the Central Electricity Generating Board (in part now Nuclear Electric) decided that the ultrasonic inspection procedures for the incredibility of failure components would be subjected to independent confirmation of their adequacy. The incorporation of validation into a large-scale inspection strategy was unique at the time (1982), indeed remains so today. The CEGB's general philosophy is one of diversity, redundancy and validation. In order to carry out independent validation of the specific procedures and ultrasonic operators to be used during the manufacture and in-service inspection of the reactor pressure vessel and steam plant components, the Inspection Validation Centre (IVC) has operated as a contractor to Nuclear Electric with special arrangements in place to guarantee independence. The setting-up and early methods of operation of IVC are briefly reviewed, the most recent operational experience summarized and the technical significance of the validations to date discussed. (author). 1 fig

  11. An Explorative Approach for Inspecting Kepler Data

    CERN Document Server

    Kügler, S D; Polsterer, K L

    2015-01-01

    The Kepler survey has provided a wealth of astrophysical knowledge by continuously monitoring over 150,000 stars. The resulting database contains thousands of examples of known variability types and at least as many that cannot be classified yet. In order to reveal the knowledge hidden in the database, we introduce a new visualisation method that allows us to inspect time series exploratively. To that end, we propose dimensionality reduction on the parameters of a model capable of representing time series as fixed-length vector representation. We show that a more refined objective function can be chosen by minimising the prediction error of the data reconstruction instead of the reconstruction of the model parameters. The proposed visualisation exhibits a strong correlation between the variability behaviour of the light curves and their physical properties. As a consequence, temperature and surface gravity can, for some stars, be directly inferred from non- (or quasi-) periodic light curves.

  12. Development of the Inspection and Diagnosis Technology for the NSSS Components Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hee; Eom, Heung Soup; Lee, Jae Cheol and others

    2005-02-15

    This project aims at the development of new technologies for a monitoring, inspection, diagnosis and evaluation of the safety related components in nuclear power plants. These technologies are required to detect the defects in the components of nuclear power plants and to prepare thoroughly against accidents. We performed the 1st stage of the study on the four issues recently focused. Thus we developed an analysis model of dynamic characteristics on the reactor internals, an on-line monitoring technology using an ultrasonic guided wave, a network based remote inspection system and an inspection robot for a control rod guide tube support pin. We also performed a lifetime estimation and degradation analysis of the NPP cables through accelerated degradation tests. The technologies developed in this project are applied to the components of nuclear power plants. The applications include a localization of the NSSS integrity monitoring system, replacement of an in-service inspection by on-line monitoring, remote inspection of the major components of the plants, lifetime estimation of the degraded plant cables, and so on. Elemental technologies obtained through the project can have great ripple effects in general industry, and can be applied to the inspection and diagnosis of the components in the other industries.

  13. A mobile robot for remote inspection of radioactive waste

    International Nuclear Information System (INIS)

    Tele-operation and remote monitoring techniques are essential and important technologies for the inspection and maintenance of the radioactive waste. A mobile robot has been developed for the application of remote monitoring and inspection of nuclear facilities, where human access is limited because of the high-level radioactive environments. The mobile robot was designed with reconfigurable crawler type of wheels attached on the front and rear side in order to pass through the ditch. The extendable mast, mounted on the mobile robot, car be extended up to 8 m vertically. The robust controller for radiation is designed in focus on electric components to prevent abnormal operation in a highly radioactivated area during reactor operation. This robot system will enhance the reliability of nuclear power facilities, and cope with the unexpected radiation accident

  14. Improvement of foundation for inspection

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization has been carrying out improvement of inspection system for nuclear plants in Japan since 2003FY. The new inspection system was introduced into nuclear power plants in-2008FY. In this project, improvement of comprehensive plant performance assessment and management tool for the new inspection system are developed. In 2012FY, a trend analysis method of the plant performance was developed with reference to the IAEA literature. And the trend analysis was tried based on the results of the comprehensive plant performance assessment of all domestic plants except Fukushima-Daiichi Nuclear Power Station. In addition, the teaching materials for QMS training guideline were made. And improvement of a quality management system evaluation support tool was performed. (author)

  15. Autonomous underwater riser inspection tool

    Energy Technology Data Exchange (ETDEWEB)

    Camerini, Claudio; Marnet, Robson [Petrobras SA, (Brazil); Freitas, Miguel; Von der Weid, Jean Pierre [CPTI/PUC-Rio, Rio de Janeiro, (Brazil); Artigas Lander, Ricardo [EngeMOVI, Curitiba, (Brazil)

    2010-07-01

    The detection of damage on the riser is a serious concern for pipeline companies. Visual examinations by remotely operated vehicle (ROV) are presently carried out to detect the defects but this process has limitations and is expensive. This paper presents the development of a new tool to ensure autonomous underwater riser inspection (AURI) that uses the riser itself for guidance. The AURI, which is autonomous in terms of control and power supply, is equipped with several cameras that perform a complete visual inspection of the riser with 100 % coverage of the external surface of the riser. The paper presents the detailed characteristics of the first AURI prototype, describes its launching procedure and provides the preliminary test results from pool testing. The results showed that the AURI is a viable system for autonomous riser inspection. Offshore tests on riser pipelines are scheduled to be performed shortly.

  16. Quality control examination on testing pesticides residues in food for agencies in charge of food safety risk monitoring and inspection%食品安全风险监测技术机构农药残留质量控制考核结果与分析

    Institute of Scientific and Technical Information of China (English)

    屈鹏峰; 杨大进; 李业鹏; 张志强; 张立实

    2012-01-01

    Objective To find out the proficiency of professionals in monitoring and inspection agencies on the determination of pesticides residue in food, and to improve the accuracy and comparability of testing results. Methods Three sets of quality control samples with the same matrix but different in concentrations of pesticides were prepared; one of blind quality control samples contained chlorpyrifos, methyl parathion, methyl pirimiphos, fenitrothion or triazophos and bifenthrin was dispatched to each inspection agency. Criteria for testing results were evaluated by Z scores; |Z|≤2 for satisfactory;2 < |Z| <3 for uncertainty and |Z|≥3 for unsatisfactory. Results The results of all quality control blind samples delivered to 162 agencies were submitted back on time. The qualitative and quantitative qualification rate for chlorpyrifos was 99. 4% and 93. 8% , for parathion-methyl was 96. 3% and 94. 9% , for bifenthrin was 95. 7% and 89.1% , for fenitrothion was 92. 0% and 89. 6% , for triazophos was 100% and 91. 9% , respectively. Conclusion The general proficiency on tested pesticide residues in food was relatively good for monitoring and inspection agencies. The agency who got unsatisfied results has recognized the problems in the process of testing; the cause of uncertainty and unsatisfactory results were found; and effective corrections were conducted to ensure the accuracy of data in the future.%目的 了解监测技术机构对食品中农药残留检测水平,确保监测数据的准确性和可比性.方法 制备3组相同基质不同浓度的农药残留质量控制样品,向每个参加单位发放一份含有毒死蜱、甲基对硫磷、甲基嘧啶磷、杀螟硫磷/三唑磷和联苯菊酯等农药的质量控制盲样;采用Z比分数法对检测结果进行评价;|Z|≤2为满意结果,2< |Z| <3为有问题结果,|Z|≥3为不满意结果.结果 162家监测机构参加考核,所有监测机构均按时提交了检测结果;毒

  17. Evaluation of inservice inspection examinatiions

    International Nuclear Information System (INIS)

    In order to evaluate the effectiveness of Section 11, Division 1, ''Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended

  18. Evaluation of inservice inspection examinatiions

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, D.A.; Cook, J.F.

    1990-05-01

    In order to evaluate the effectiveness of Section 11, Division 1, ``Rules for Inservice Inspection of Nuclear Power Plant Components,`` of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended.

  19. Evaluation of inservice inspection examinatiions

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, D.A.; Cook, J.F.

    1990-05-01

    In order to evaluate the effectiveness of Section 11, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended.

  20. Economics important in selecting monitoring techniques

    International Nuclear Information System (INIS)

    Failure/risk costs need to be considered when deciding on the type of corrosion monitoring and inspection. Locations with high-pressure, high-velocity streams need closer monitoring. This article discusses the risks associated with different types of fluid streams and the various inspection techniques that can range from a low-cost visual examination to mechanical calipers and electromagnetic, radiographic, and ultrasonic tools

  1. In service inspection of pipes based on risk methods

    International Nuclear Information System (INIS)

    , recommending only flight monitoring and pressure and flight tests for 13 considered segments of low risk. With the above-mentioned a substantial saving is obtained in the costs by inspection for the plant, avoiding the potential personnel's lesions by means of the reduction of the construction of scaffolds, removal of asbestos, removal of insulations and welding polishing. (Author)

  2. Planning Annual Shutdown Inspection for BFB Boiler

    OpenAIRE

    Sorsa, Tatu

    2014-01-01

    The goal of this thesis was to create an illustrative guidebook of annual inspection planning for BFB boiler to help power plant operator when planning of annual inspection is topical. This thesis was made for Andritz Oy and it is based on inspection reports and experiences of BFB boiler’s maintenance and inspection staff. In this thesis it is shown how to plan an annual inspection for BFB boiler and thesis gives good tools and hints for operator to manage inspection from the beginning ...

  3. Pulse-echo ultrasonic inspection system for in-situ nondestructive inspection of Space Shuttle RCC heat shields.

    Energy Technology Data Exchange (ETDEWEB)

    Roach, Dennis Patrick; Walkington, Phillip D.; Rackow, Kirk A.

    2005-06-01

    The reinforced carbon-carbon (RCC) heat shield components on the Space Shuttle's wings must withstand harsh atmospheric reentry environments where the wing leading edge can reach temperatures of 3,000 F. Potential damage includes impact damage, micro cracks, oxidation in the silicon carbide-to-carbon-carbon layers, and interlaminar disbonds. Since accumulated damage in the thick, carbon-carbon and silicon-carbide layers of the heat shields can lead to catastrophic failure of the Shuttle's heat protection system, it was essential for NASA to institute an accurate health monitoring program. NASA's goal was to obtain turnkey inspection systems that could certify the integrity of the Shuttle heat shields prior to each mission. Because of the possibility of damaging the heat shields during removal, the NDI devices must be deployed without removing the leading edge panels from the wing. Recently, NASA selected a multi-method approach for inspecting the wing leading edge which includes eddy current, thermography, and ultrasonics. The complementary superposition of these three inspection techniques produces a rigorous Orbiter certification process that can reliably detect the array of flaws expected in the Shuttle's heat shields. Sandia Labs produced an in-situ ultrasonic inspection method while NASA Langley developed the eddy current and thermographic techniques. An extensive validation process, including blind inspections monitored by NASA officials, demonstrated the ability of these inspection systems to meet the accuracy, sensitivity, and reliability requirements. This report presents the ultrasonic NDI development process and the final hardware configuration. The work included the use of flight hardware and scrap heat shield panels to discover and overcome the obstacles associated with damage detection in the RCC material. Optimum combinations of custom ultrasonic probes and data analyses were merged with the inspection procedures needed to

  4. Program for establishing long-time flight service performance of composite materials in the center wing structure of C-130 aircraft. Phase 5: Flight service and inspection

    Science.gov (United States)

    Kizer, J. A.

    1981-01-01

    Inspections of the C-130 composite-reinforced center wings were conducted over the flight service monitoring period of more than six years. Twelve inspections were conducted on each of the two C-130H airplanes having composite reinforced center wing boxes. Each inspection consisted of visual and ultrasonic inspection of the selective boron-epoxy reinforced center wings which included the inspection of the boron-epoxy laminates and the boron-epoxy reinforcement/aluminum structure adhesive bondlines. During the flight service monitoring period, the two C-130H aircraft accumulated more than 10,000 flight hours and no defects were detected in the inspections over this period. The successful performance of the C-130H aircraft with composite-reinforced center wings allowed the transfer of the responsibilities of inspecting and maintaining these two aircraft to the U. S. Air Force.

  5. Automated reticle inspection data analysis for wafer fabs

    Science.gov (United States)

    Summers, Derek; Chen, Gong; Reese, Bryan; Hutchinson, Trent; Liesching, Marcus; Ying, Hai; Dover, Russell

    2009-04-01

    To minimize potential wafer yield loss due to mask defects, most wafer fabs implement some form of reticle inspection system to monitor photomask quality in high-volume wafer manufacturing environments. Traditionally, experienced operators review reticle defects found by an inspection tool and then manually classify each defect as 'pass, warn, or fail' based on its size and location. However, in the event reticle defects are suspected of causing repeating wafer defects on a completed wafer, potential defects on all associated reticles must be manually searched on a layer-by-layer basis in an effort to identify the reticle responsible for the wafer yield loss. This 'problem reticle' search process is a very tedious and time-consuming task and may cause extended manufacturing line-down situations. Often times, Process Engineers and other team members need to manually investigate several reticle inspection reports to determine if yield loss can be tied to a specific layer. Because of the very nature of this detailed work, calculation errors may occur resulting in an incorrect root cause analysis effort. These delays waste valuable resources that could be spent working on other more productive activities. This paper examines an automated software solution for converting KLA-Tencor reticle inspection defect maps into a format compatible with KLA-Tencor's Klarity Defect(R) data analysis database. The objective is to use the graphical charting capabilities of Klarity Defect to reveal a clearer understanding of defect trends for individual reticle layers or entire mask sets. Automated analysis features include reticle defect count trend analysis and potentially stacking reticle defect maps for signature analysis against wafer inspection defect data. Other possible benefits include optimizing reticle inspection sample plans in an effort to support "lean manufacturing" initiatives for wafer fabs.

  6. Inspection of environmental conditions 1991

    International Nuclear Information System (INIS)

    A comprehensive survey of environmentally protective activities (including inspections or surveillance, planning, the giving of guidelines and approvals) carried out by Danish local authorities and municipalities on pollutive/environmental conditions related to public services, companies and agriculture during 1991. Administrative details are given. The survey is based on the accounts of the inspections produced by the individual authorities. Information is given on the extent of these projects, the nature of the activities involved and the evaluation of them made by the (Danish) National Agency for Environmental Protection. In the appendices data is presented on the percentage of companies visited, the amounts of oil and chemical industrial wastes, the visited farms, the average number of domestic animals held, the nitrate content of drinking water in a number of specified waterworks, the number of objects of inspection, the number of enforcements in relation to the number of inspections and organic substances discharged from sewage works. Other related data, for example on the management of wastes, illustrate the detailed text. (AB)

  7. Artificial Intelligence Assists Ultrasonic Inspection

    Science.gov (United States)

    Schaefer, Lloyd A.; Willenberg, James D.

    1992-01-01

    Subtle indications of flaws extracted from ultrasonic waveforms. Ultrasonic-inspection system uses artificial intelligence to help in identification of hidden flaws in electron-beam-welded castings. System involves application of flaw-classification logic to analysis of ultrasonic waveforms.

  8. Nuclear pipework - welding and inspection

    International Nuclear Information System (INIS)

    The subject is covered in sections: introduction emphasizing need for perfection in welding nuclear pipework; detailed procedures (British Standards, TIG welding, automatic orbital TIG welding machines); unacceptable faults; improving performance (higher quality of commercially-available grades of stainless steels); auto welding; testing 'nuclear' welding; safe working (standard specifications, radiography); training; radiographic techniques; radiographic procedures; other inspections. (U.K.)

  9. FAA Fluorescent Penetrant Laboratory Inspections

    Energy Technology Data Exchange (ETDEWEB)

    WINDES,CONNOR L.; MOORE,DAVID G.

    2000-08-02

    The Federal Aviation Administration Airworthiness Assurance NDI Validation Center currently assesses the capability of various non-destructive inspection (NDI) methods used for analyzing aircraft components. The focus of one such exercise is to evaluate the sensitivity of fluorescent liquid penetrant inspection. A baseline procedure using the water-washable fluorescent penetrant method defines a foundation for comparing the brightness of low cycle fatigue cracks in titanium test panels. The analysis of deviations in the baseline procedure will determine an acceptable range of operation for the steps in the inspection process. The data also gives insight into the depth of each crack and which step(s) of the inspection process most affect penetrant sensitivities. A set of six low cycle fatigue cracks produced in 6.35-mm thick Ti-6Al-4V specimens was used to conduct the experiments to produce sensitivity data. The results will document the consistency of the crack readings and compare previous experiments to find the best parameters for water-washable penetrant.

  10. Fuel-element inspection stand in the cooling pond of an atomic power plant

    International Nuclear Information System (INIS)

    A fuel-element inspection stand has been built in the cooling pool of the second power unit at the Ignalina Atomic Power Plant for the purpose of monitoring fuel elements unloaded from the reactor and for performing research involving the acquisition and analysis of statistically significant information concerning the reliability and efficiency of fuel elements and fuel bundles. The uses and specifications of the fuel-element inspection stand are given in this paper. 1 ref., 4 figs

  11. Disposal technique inspect of France's uranium mine and mill facilities decommissioning

    International Nuclear Information System (INIS)

    Invited by Linet F.L., the director of France Atomic Energy Committee, China disposal technique inspection delegation on uranium mine and mill facilities decommissioning (UMMFD) inspected France's UMMFD disposal techniques on Oct. 7∼30, 1997. Introduces in detail the disposal Standard, environmental radiation monitoring and evaluation, covering experiment and decommissioning disposal procedure, and gives certain case of France's uranium mine and mill facilities decommissioning disposal

  12. Design of inspection and maintenance models based on the CCC-chart

    OpenAIRE

    Chan, LY

    2003-01-01

    In this research, six maintenance models are constructed based on whether minor inspection, major inspection, minor maintenance and major maintenance are performed on a system. The system to study is a production process in which items produced can be classified as either conforming or nonconforming, and a statistical process control chart called CCC-chart (cumulative count control chart) can be applied to monitor the process. The maintenance models are analyzed quantitatively, and selection ...

  13. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Silvas, A. J. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site; Lantow, Tiffany A. [National Security Technologies, LLC, Las Vegas, NV (United States). Nevada Test Site

    2015-03-25

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2014 and includes inspection and repair activities completed at the following CAUs; CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Photographs taken during inspections are included in Appendix D. The annual post-closure inspections were conducted on May 28, 2014. Maintenance was required at CAU 407. Animal burrows were backfilled and erosion repairs were performed. Vegetation monitoring was performed at CAU 407 in June 2014. The vegetation monitoring report is included in Appendix E.

  14. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

    International Nuclear Information System (INIS)

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 426: Cactus Spring Waste Trenches (TTR); (5) CAU 453: Area 9 UXO Landfill (TTR); (6) CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR); and (7) CAU 487: Thunderwell Site (TTR). The annual post-closure inspections were conducted May 5-6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections

  15. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2010-05-28

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2009 and includes inspection and repair activities completed at the following seven CAUs: · CAU 400: Bomblet Pit and Five Points Landfill (TTR) · CAU 407: Roller Coaster RadSafe Area (TTR) · CAU 424: Area 3 Landfill Complexes (TTR) · CAU 426: Cactus Spring Waste Trenches (TTR) · CAU 453: Area 9 UXO Landfill (TTR) · CAU 484: Surface Debris, Waste Sites, and Burn Area (TTR) · CAU 487: Thunderwell Site (TTR) The annual post-closure inspections were conducted May 5–6, 2009. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2009, and the vegetation monitoring report is included in Attachment F. Maintenance was performed at CAU 453. Animal burrows observed during the annual inspection were backfilled, and a depression was restored to grade on June 25, 2009. Post-closure site inspections should continue as scheduled. Vegetation survey inspections have been conducted annually at CAUs 400, 404, 407, and 426. Discontinuation of vegetation surveys is recommended at the CAU 400 Bomblet Pit and CAU 426, which have been successfully revegetated. Discontinuation of vegetation surveys is also recommended at CAU 404, which has been changed to an administrative closure with no inspections required. Vegetation

  16. Reliability Assessment and Reliability-Based Inspection and Maintenance of Offshore Wind Turbines

    DEFF Research Database (Denmark)

    Ramírez, José G. Rangel; Sørensen, John Dalsgaard

    2009-01-01

    Probabilistic methodologies represent an important tool to identify the suitable strategy to inspect and deal with the deterioration in structures such as offshore wind turbines (OWT). Reliability based methods such as Risk Based Inspection (RBI) planning may represent a proper methodology to...... optimize inspection and maintenance (I&M) efforts, entailing to a suitable life-cycle performance without neglecting the economical aspect. Moreover, the integration of condition monitoring information (CMI) can be done through probabilistic inference. In this work, a reliability-based I&M planning OWT is...

  17. Locating Mechanical Damages Using Magnetic Flux Leakage Inspection in Gas Pipeline System

    International Nuclear Information System (INIS)

    Gas transmission pipelines are often inspected and monitored using the magnetic flux leakage method. An inspection vehicle known as a 'pig' is launched into the pipeline and conveyed along the pipe by the pressure of natural gas. The pig contains a magnetizer, an array of sensors and a microprocessor-based data acquisition system for logging data. This paper describes magnetic flux leakage (MFL) signal processing used for detecting mechanical damages during an in-line inspection. The overall approach employs noise removal and clustering technique. The proposed method is computationally efficient and can easily be implemented. Results are presented and verified by field tests from an application of the signal processing

  18. CAT -- computer aided testing for resonant inspection

    International Nuclear Information System (INIS)

    Application of computer technology relates to inspection and quality control. The computer aided testing (CAT) can be used to analyze various NDT technologies, such as eddy current, ultrasonics, and resonant inspection

  19. Allegheny County Housing and Community Environment Inspections

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — Residential housing inspections and inspections in response to complaints for community environment problems, such as open vacant structures, vacant lots with...

  20. Automated Ply Inspection (API) for AFP Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The Automated Ply Inspection (API) system autonomously inspects layups created by high speed automated fiber placement (AFP) machines. API comprises a high accuracy...

  1. Tecnology Development for Robotic Surface Inspection

    Science.gov (United States)

    Volpe, Richard; Balaram, J. Bob

    1994-01-01

    For the past three years at JPL, NASA has been sponsoring the Remote Surface Inspection Project to develop the technology needed for doing periodic and on-demand inspection of space borne platforms, in particular Space Station Freedom.

  2. Experimental Stress Analysis at Railway Inspection Pit

    Directory of Open Access Journals (Sweden)

    Nicuşor Laurentiu Zaharia

    2008-10-01

    Full Text Available Railway inspection pits are used in railway halls. The purpose of inspection pits is to allow the working under the vehicle. Inspection pits can be found in locomotive depots, factories etc. The new design for a inspection pit in a railway hall involve tests in purpose of homologations the railway infrastructure. Before the homologation committee meeting, tests are made; after the test, a testing report is made which it will be part at homologation documents.

  3. Preparing and organizing inspection and maintenance

    International Nuclear Information System (INIS)

    The philosophy and goals of maintenance are discussed. The main principles in organizing the maintenance of the Loviisa power plant are: the people responsible for maintenance during operation are also responsible for maintenance during outages; outside contractors are used for the peak loads during outages but the planning and monitoring of outages is the responsibility of the plant personnel. Technically skilled and highly motivated personnel is the most important prerequisite of success. Loviisa has for several years very successfully utilized two different types of salary bonus system. The reloading outage bonus system gives more money per hour during the outage and an additional increase for all plant people participating in the outage work, if the duration of the outage is shorter than planned. The amount of the extra bonus depends on the final duration of the outage. The operation and maintenance of the Loviisa plant is based on quality assurance, operation and maintenance procedures. The annual and long-term plan of actions are controlled by regular planning meetings which utilize all reports produced by the maintenance groups. The technical outage report contains all technical information gathered during the outages according to the preventive maintenance and in-service inspection programs. The condition monitoring programs of the plant components were developed by the Research Laboratories of Imatran Voima and financed by the plant. (Z.S.) 9 figs., 5 refs

  4. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    This periodical covers the results of inspections performed by the NRC's Vendor Inspection Branch that have been distributed to the inspected organizations during the period form January 1994 through March 1994. A list of selected bulletins and information notices involving vendor issues and copies of pertinent correspondence involving vendor issues are also included in this periodical

  5. Generator acceptance test and inspection report

    International Nuclear Information System (INIS)

    This Acceptance Test Report(ATR) is the completed testing and inspection of the new portable generator. The testing and inspection is to verify that the generator provided by the vendor meets the requirements of specification WHC-S-0252, Revision 2. Attached is various other documentation to support the inspection and testing

  6. 42 CFR 73.18 - Inspections.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Inspections. 73.18 Section 73.18 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES QUARANTINE, INSPECTION, LICENSING SELECT AGENTS AND TOXINS § 73.18 Inspections. (a) Without prior notification, the HHS Secretary, shall...

  7. 9 CFR 354.10 - Inspection service.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inspection service. 354.10 Section 354.10 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY... CERTIFICATION VOLUNTARY INSPECTION OF RABBITS AND EDIBLE PRODUCTS THEREOF Basis of Service § 354.10...

  8. Modelling in Optimal Inspection and Repair

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Rackwitz, R.; Faber, M.H.;

    1991-01-01

    A model for reliability based optimal inspection and repair strategies is described. The total expected costs in the lifetime is minimized with the number of inspections, the inspection times and efforts, the repair crack size limit and a design parameter as optimization variables. The equivalenc...

  9. 24 CFR 3282.362 - Production Inspection Primary Inspection Agencies (IPIAs).

    Science.gov (United States)

    2010-04-01

    ... section and of § 3280.5 of chapter XX of 24 CFR. The data plate shall be furnished by the manufacturer and... 24 Housing and Urban Development 5 2010-04-01 2010-04-01 false Production Inspection Primary... REGULATIONS Primary Inspection Agencies § 3282.362 Production Inspection Primary Inspection Agencies...

  10. In-Service Inspection system for coolant channels of Indian PHWRS - evolution and experience

    International Nuclear Information System (INIS)

    In-Service Inspection (ISI) is the most important of all periodic monitoring and surveillance activities for assuring the structural integrity of coolant channels in the life extension and management of pressurized heavy water reactors (PHWR-CANDU). Indian PHWRs (220 MWe) are characterized by consists by 306 coolant channels in each unit. These channels have to be inspected for various parameters over the operating life of the reactor. ISI of coolant channels necessitated the indigenous development of an inspection system called BARCIS (BARC Channel Inspection System) at Bhabha Atomic Research Center. BARCIS consists of mainly three parts; drive and control unit, special sealing plug and an inspection head carrying various NDT sensors. Five such systems have been built and deployed at various power plants. The paper deals with the development of the BARCIS system for meeting the ISI requirements of coolant channels, development cycle of this system from its conception to evolution to the present state, challenges, data generated and experience gained (ISI of nearly 900 coolant channels has been completed). Prior to BARCIS, pressure tube gauging equipment for pre-service inspection of coolant tubes was developed in 1980. Moreover a tool for ISI of coolant channels in dry condition was developed in 1990. The paper also describes evolution of various contingency procedures and devices developed over the last one decade. Future plans taking into account technological advancement, changes in the scope of inspection due to design and operating experiences and plant layout will also be covered. The paper describes the efforts put in to develop drive and control mechanism to suit the different vault layouts. The drive mechanism is responsible for linear and rotary movement of the inspection head to carry out 100% volumetric inspection. Special emphasis has been laid on the safety devices required during the inspection activity. Special measures for heavy water retention in

  11. Supplementing Public Health Inspection via Social Media.

    Science.gov (United States)

    Schomberg, John P; Haimson, Oliver L; Hayes, Gillian R; Anton-Culver, Hoda

    2016-01-01

    Foodborne illness is prevented by inspection and surveillance conducted by health departments across America. Appropriate restaurant behavior is enforced and monitored via public health inspections. However, surveillance coverage provided by state and local health departments is insufficient in preventing the rising number of foodborne illness outbreaks. To address this need for improved surveillance coverage we conducted a supplementary form of public health surveillance using social media data: Yelp.com restaurant reviews in the city of San Francisco. Yelp is a social media site where users post reviews and rate restaurants they have personally visited. Presence of keywords related to health code regulations and foodborne illness symptoms, number of restaurant reviews, number of Yelp stars, and restaurant price range were included in a model predicting a restaurant's likelihood of health code violation measured by the assigned San Francisco public health code rating. For a list of major health code violations see (S1 Table). We built the predictive model using 71,360 Yelp reviews of restaurants in the San Francisco Bay Area. The predictive model was able to predict health code violations in 78% of the restaurants receiving serious citations in our pilot study of 440 restaurants. Training and validation data sets each pulled data from 220 restaurants in San Francisco. Keyword analysis of free text within Yelp not only improved detection of high-risk restaurants, but it also served to identify specific risk factors related to health code violation. To further validate our model we applied the model generated in our pilot study to Yelp data from 1,542 restaurants in San Francisco. The model achieved 91% sensitivity 74% specificity, area under the receiver operator curve of 98%, and positive predictive value of 29% (given a substandard health code rating prevalence of 10%). When our model was applied to restaurant reviews in New York City we achieved 74% sensitivity

  12. Radiographic inspection on offshore platforms

    International Nuclear Information System (INIS)

    One of the great challenges for non-destructive inspection is on offshore platforms, where safety is a critical issue. Inspection by gammagraphy is practically forbidden on the platform deck due to problems to personnel safety and radiological protection. Ir-192 sources are used and the risk of an accident with loss of radioisotope must be considered. It is unfeasible to use gammagraphy, because in case of an accident the rapid evacuation from the platform would be impossible. This problem does not occur when X-ray equipment is used as the radiation source. The limited practicality and portability of the X-ray equipment have prevented its use as a replacement for the gammagraphy. This paper presents the preliminary tests to see the viable use of radiographic tests with constant potential on offshore platforms. (author). 2 refs., 1 fig., 2 tabs, 3 photos

  13. Vehicle and cargo inspection system

    Science.gov (United States)

    Verbinski, Victor V.; Orphan, Victor J.

    1997-02-01

    Vehicle and Cargo Inspection System (VACIS) is comprised of a 1 Curie 137Cs gamma-ray source in a shield and collimator which produces a fan-shaped beam designed to intercept a vertical array of gama-ray detectors contained in a tower structure. The source and detector modules straddle the vehicle or container being inspected and are mounted on self-propelled trolleys which travel in synchronization along two parallel tracks covering the length of the scanned object. The signals from the gamma-ray detector array are processed and displayed so as to produce a 2D gamma-radiographic image of the object. Testing of the system on a variety of empty and lightly-loaded vehicles and containers has demonstrated the effectiveness of VACIS in detecting hidden contraband. For example, a small sample of cocaine only 1.5 inches thick was readily detected in a container.

  14. Drum inspection robots: Application development

    International Nuclear Information System (INIS)

    Throughout the Department of Energy (DOE), drums containing mixed and low level stored waste are inspected, as mandated by the Resource Conservation and Recovery Act (RCRA) and other regulations. The inspections are intended to prevent leaks by finding corrosion long before the drums are breached. The DOE Office of Science and Technology (OST) has sponsored efforts towards the development of robotic drum inspectors. This emerging application for mobile and remote sensing has broad applicability for DOE and commercial waste storage areas. Three full scale robot prototypes have been under development, and another project has prototyped a novel technique to analyze robotically collected drum images. In general, the robots consist of a mobile, self-navigating base vehicle, outfitted with sensor packages so that rust and other corrosion cues can be automatically identified. They promise the potential to lower radiation dose and operator effort required, while improving diligence, consistency, and documentation

  15. CRDM nozzle inspection/repair

    International Nuclear Information System (INIS)

    The susceptibility of Alloy 600 to Primary Water Stress Corrosion Cracking (PWSCC) continues to plague nuclear power plants. Recently, the problem PWSCC has manifested itself in Control Rod Drive Mechanism (CRDM) head penetrations in nuclear plants in Europe and the U.S. B and W Nuclear Technologies (BWNT) has been involved in responding to this potentially industry-wide concern through the B and W Owners Group (B and WOG). The program also includes work performed in cooperation with the Nuclear Energy Institute (NEI) Task Force and other Owners Groups. BWNT, building on our parent company's (Framatome) technology, has also developed a fully integrated service package and robotic manipulator to inspect and repair CRDM head penetrations for U.S. utilities. This paper describes the work performed by the B and WOG to address this issue globally, and the overall range of inspection and repair tooling and processes developed by Framatome and BWNT to address this issue. (author). 6 figs

  16. Development of the Inspection and Diagnosis Technology for the NSSS Components Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hee; Eom, Heung Soup; Lee, Jae Cheol (and others)

    2007-02-15

    This project is to develop and demonstrate new technologies for a monitoring, inspection, diagnosis and evaluation of the safety related components in nuclear power plants. These technologies are required to detect the defects in the components of nuclear power plants and to prepare thoroughly against accidents. We studied on the four issues recently focused. Thus we developed an impact analysis model of the reactor and steam generator, and diagnosis software of the reactor internals. As an on-line monitoring technology using an ultrasonic guided wave, we developed a new method enhancing the S/N ratio of the weak signal based on time reversal technique. A network based remote inspection system and an inspection robot for reactor vessel head penetration was developed. We also performed a lifetime estimation and degradation analysis of the NPP cables through accelerated degradation tests. The technologies developed in this project are applied to the components of nuclear power plants. The applications include a localization of the NSSS integrity monitoring system, replacement of an in-service inspection by on-line monitoring, remote inspection of the major components of the plants, lifetime estimation of the degraded plant cables, and so on.

  17. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2008-06-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

  18. Post-Closure Inspection Report for the Tonopah Test Range, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2007-06-01

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2006 and includes inspection and repair activities completed at the following nine CAUs: CAU 400: Bomblet Pit and Five Points Landfill (TTR); CAU 404: Roller Coaster Lagoons and Trench (TTR); CAU 407: Roller Coaster RadSafe Area (TTR); CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); CAU 424: Area 3 Landfill Complexes (TTR); CAU 426: Cactus Spring Waste Trenches (TTR); CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); CAU 453: Area 9 UXO Landfill (TTR); and CAU 487: Thunderwell Site (TTR). Post-closure inspections were conducted on May 9, 2006, May 31, 2006, and November 15, 2006. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2006, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 400, CAU 407, CAU 426, CAU 453, and CAU 487 in 2006. During the May inspection of CAU 400, it was identified that the east and west sections of chickenwire fencing beyond the standard fencing were damaged; they were repaired in June 2006. Also in June 2006, the southeast corner fence post and one warning sign at CAU 407 were reinforced and reattached, the perimeter fencing adjacent to the gate at CAU 426 was tightened, and large animal

  19. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2007

    International Nuclear Information System (INIS)

    This report provides the results of the semiannual post-closure inspections conducted at the closed Corrective Action Unit (CAU) sites located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2007 and includes inspection and repair activities completed at the following nine CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR); (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2, 6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). In a letter from the Nevada Division of Environmental Protection (NDEP) dated December 5, 2006, NDEP concurred with the request to reduce the frequency of post-closure inspections of CAUs at TTR to an annual frequency. This letter is included in Attachment B. Post-closure inspections were conducted on May 15-16, 2007. All inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Attachment B, with the exception of CAU 400. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. The inspection checklists for each site inspection are included in Attachment C, the field notes are included in Attachment D, and the site photographs are included in Attachment E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in May 2007, and the vegetation monitoring report is included in Attachment F. Maintenance and/or repairs were performed at CAU 453. Animal burrows observed during the annual inspection at CAU 453 were backfilled on August 1, 2007. At this time, the TTR post-closure site inspections should continue as

  20. Inspection technologies -Development of national safeguards technology-

    International Nuclear Information System (INIS)

    17 facility regulations prepared by nuclear facilities according to the Ministerial Notices were evaluated. Safeguards inspection activities under Safeguards are described. Safeguards inspection equipments and operation manuals to be used for national inspection are also described. Safeguards report are produced and submitted to MOST by using the computerized nuclear material accounting system at state level. National inspection support system are developed to produce the on-site information for domestic inspection. Planning and establishment of policy for nuclear control of nuclear materials, international cooperation for nuclear control, CTBT, strengthening of international safeguards system, and the supply of PWRs to North Korea are also described. (author). 43 tabs., 39 figs

  1. 2015 Bridge Inspection ERC Training

    OpenAIRE

    Dougherty, Merril

    2015-01-01

    This presentation will discuss recent changes to the County Bridge Inspection Program from the perspective of both the FHWA and INDOT. We will also discuss the responsibilities of the local public agency’s (LPA’s) employee in responsible charge (ERC) with respect to managing this program. As this course is a yearly requirement, all county ERCs are encouraged to attend. Pre-registering is strongly encouraged by e-mailing your contact information to .

  2. Inspection device for buried equipment

    International Nuclear Information System (INIS)

    In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

  3. Using Pipe For Inspection Applications

    Science.gov (United States)

    Luck, Randall L.

    1987-05-01

    This paper will describe PIPE and how its capabilities can be used for inspection applications. PIPE is a high performance parallel processor with an architecture specifically designed for the processing of video images at up to 60 fields per second. The unit is modular and programmable. It processes sequences of images through a pipeline of point processors, image buffers and arithmetic or Boolean neighborhood operators. There are multiple data pathways between the stages in forward, recursive and backward directions that allow images to interact in many useful ways. Due to its architecture, PIPE inherently allows the processing of many images simultaneously for working with dynamic scenes or multiple combinations of the same image. Although originally designed for robot guidance applications, PIPE has many features that make it well suited for use in inspection. For these inspection applications, this multiple image capability allows the pipelining of different processes on different images at the same time. In addition, a programmable region of interest capability allows different processes to be run on different areas of the same image. Illustrations of some these techniques will be presented.

  4. Optimisation of sonic thermographic inspection

    Science.gov (United States)

    Tsoi, Kelly A.; Yousif, Khalid; Rajic, Nik; Powlesland, Ian

    2009-03-01

    A versatile and broad-field technique, sonic thermography uses high intensity acoustic waves to induce frictional heating at defect locations and the thermal signature is then detected using IR imaging. Sonic thermography has the potential to be used as a quantitative technique for difficult inspection problems. One example is the inspection of interference fit fasteners. In the case of poorly fitted interference fasteners, the acoustic waves induce relative motion between the fastener and host, causing frictional heating which can then be detected. The preliminary results of an inspection of interference fit levels in fastened metallic plates, reminiscent of the F-111C wing skin, are discussed. By improving the repeatability of the acoustic energy transfer, the heat detected using the IR thermographic system can be correlated to the interference fit levels of the fasteners. The results provide encouragement for the development of a quantitative assessment capability, however one of the remaining critical issues, which has hindered the use of sonic thermography as a quantitative technique, is the poor repeatability of acoustic excitations. This paper will also report on an experimental study which investigates this repeatability issue, in particular the role of the interface material used between the horn tip and the structure to enhance energy transfer.

  5. Intelligent Automated Nuclear Fuel Pellet Inspection System

    International Nuclear Information System (INIS)

    At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

  6. Generative inspection process planner for integrated production

    Energy Technology Data Exchange (ETDEWEB)

    Brown, C.W. (Allied-Signal Aerospace Co., Kansas City, MO (USA). Kansas City Div.); Gyorog, D.A. (Kansas Univ., Lawrence, KS (USA). Dept. of Mechanical Engineering)

    1990-04-01

    This work describes the design prototype development of a generative process planning system for dimensional inspection. The system, IPPEX (Inspection Process Planning EXpert), is a rule-based expert system for integrated production. Using as advanced product modeler, relational databases, and artificial intelligence techniques, IPPEX generates the process plan and part program for the dimensional inspection of products using CMMs. Through an application interface, the IPPEX system software accesses product definition from the product modeler. The modeler is a solid geometric modeler coupled with a dimension and tolerance modeler. Resource data regarding the machines, probes, and fixtures are queried from databases. IPPEX represents inspection process knowledge as production rules and incorporates an embedded inference engine to perform decision making. The IPPEX system, its functional architecture, system architecture, system approach, product modeling environment, inspection features, inspection knowledge, hierarchical planning strategy, user interface formats, and other fundamental issues related to inspection planning and part programming for CMMs are described. 27 refs., 16 figs., 4 tabs.

  7. Inspection of dissimilar metal welds in reactor pressure vessels in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Gadea, J.R.; Regidor, J.J.; Pelaez, J.A.; Serrano, P. [Tecnatom, S.A., San Sebastian de los Reyes, Madrid (Spain)

    2011-07-01

    MRP-139 recommendations for inspection of dissimilar metal (DM) welds in PWR vessels were launched in the last years in the USA. Basically, it increases the frequency of the examinations in these type of welds, with major emphasis in the hot loops, adding one intermediate inspection at the ten years interval in outlet nozzles. The spanish nuclear power plants (NPP's) have begun the implementation of this type of inspections on the vessel nozzles DM welds. As this type of inspections could have an impact in the critical path duration of the outage, it is necessary the use of a mechanical equipment able to examine the nozzles DM welds in a short vessel occupation time (VOT) with high quality, qualified techniques and minimum requirements of the refuelling platform. Tecnatom undertook the design and development of a new more advanced equipment, named TENIS-DM, for implementing the reactor pressure vessel (RPV) nozzles examination. This equipment was designed in order to accomplish the stringent requirements and the updated examination techniques; it was used for the inspection of the DM welds of Asco 1 NPP inlet and outlet nozzles in March 2011. Examination techniques and procedures were qualified through the GRUVAL validation program, based on ENIC methodology. Mechanical scanner was equipped with a large number of examination probes, and TV cameras -for visual inspection and also for monitoring the ultrasonic inspections. A remote operated submarine was also used to give support to the operational personnel during the manipulation of the equipment and its movements from one nozzle to the others. During two months before the inspection, tests of the complete inspection system were made on a nozzle mock-up installed in a 4 meters deep well at Tecnatom's facilities; this scenario was also used during the training sessions of the inspection crew. The defined technical and practical objectives were achieved: use of qualified techniques and minimal impact on the

  8. Inspection of dissimilar metal welds in reactor pressure vessels in Spain

    International Nuclear Information System (INIS)

    MRP-139 recommendations for inspection of dissimilar metal (DM) welds in PWR vessels were launched in the last years in the USA. Basically, it increases the frequency of the examinations in these type of welds, with major emphasis in the hot loops, adding one intermediate inspection at the ten years interval in outlet nozzles. The spanish nuclear power plants (NPP's) have begun the implementation of this type of inspections on the vessel nozzles DM welds. As this type of inspections could have an impact in the critical path duration of the outage, it is necessary the use of a mechanical equipment able to examine the nozzles DM welds in a short vessel occupation time (VOT) with high quality, qualified techniques and minimum requirements of the refuelling platform. Tecnatom undertook the design and development of a new more advanced equipment, named TENIS-DM, for implementing the reactor pressure vessel (RPV) nozzles examination. This equipment was designed in order to accomplish the stringent requirements and the updated examination techniques; it was used for the inspection of the DM welds of Asco 1 NPP inlet and outlet nozzles in March 2011. Examination techniques and procedures were qualified through the GRUVAL validation program, based on ENIC methodology. Mechanical scanner was equipped with a large number of examination probes, and TV cameras -for visual inspection and also for monitoring the ultrasonic inspections. A remote operated submarine was also used to give support to the operational personnel during the manipulation of the equipment and its movements from one nozzle to the others. During two months before the inspection, tests of the complete inspection system were made on a nozzle mock-up installed in a 4 meters deep well at Tecnatom's facilities; this scenario was also used during the training sessions of the inspection crew. The defined technical and practical objectives were achieved: use of qualified techniques and minimal impact on the critical

  9. Ageing management, in service inspection and exceptional maintenance

    International Nuclear Information System (INIS)

    Actions implemented by EDF in the field of maintenance in order to control the ageing of Nuclear Power Plants (NPPs) Structures, Systems and Components and to ensure an operation of NPPs in compliance with safety requirements are described. Routine maintenance, exceptional maintenance, in service inspections associated with an efficient monitoring and a thorough analysis with the experience feedback, contribute to this control and has to be adapted to each component, taking into account the ageing phenomena brought into play. Several examples implemented by EDF on Nuclear Island or Conventional Island equipments are introduced: Reactor Vessel Heads replacement strategy, Steam Generators replacement strategy, I and C systems long term maintenance strategy, Generator Stators refurbishment strategy. Maintenance strategies are based on in service inspection activities, using qualified examination methods. (author)

  10. Evaluation of NRC maintenance team inspection reports for managing aging

    International Nuclear Information System (INIS)

    A nuclear power plant's maintenance program is the principal vehicle through which age-related degradation is managed. Over the past two years, the NRC [Nuclear Regulatory Commission] has evaluated the maintenance program of every nuclear power plant in the U.S. The reports issued on these in-depth team inspections have been reviewed to ascertain the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear power plant systems, structures, and components. Selected results of this review are presented in this paper, including examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue are also discussed. 6 refs., 1 tab

  11. Advances in in situ inspection of automated fiber placement systems

    Science.gov (United States)

    Juarez, Peter D.; Cramer, K. Elliott; Seebo, Jeffrey P.

    2016-05-01

    Automated Fiber Placement (AFP) systems have been developed to help take advantage of the tailorability of composite structures in aerospace applications. AFP systems allow the repeatable placement of uncured, spool fed, preimpregnated carbon fiber tape (tows) onto substrates in desired thicknesses and orientations. This automated process can incur defects, such as overlapping tow lines, which can severely undermine the structural integrity of the part. Current defect detection and abatement methods are very labor intensive, and still mostly rely on human manual inspection. Proposed is a thermographic in situ inspection technique which monitors tow placement with an on board thermal camera using the preheated substrate as a through transmission heat source. An investigation of the concept is conducted, and preliminary laboratory results are presented. Also included will be a brief overview of other emerging technologies that tackle the same issue.

  12. Advanced in In Situ Inspection of Automated Fiber Placement Systems

    Science.gov (United States)

    Juarez, Peter D.; Cramer, K. Elliott; Seebo, Jeffrey P.

    2016-01-01

    Automated Fiber Placement (AFP) systems have been developed to help take advantage of the tailorability of composite structures in aerospace applications. AFP systems allow the repeatable placement of uncured, spool fed, preimpregnated carbon fiber tape (tows) onto substrates in desired thicknesses and orientations. This automated process can incur defects, such as overlapping tow lines, which can severely undermine the structural integrity of the part. Current defect detection and abatement methods are very labor intensive, and still mostly rely on human manual inspection. Proposed is a thermographic in situ inspection technique which monitors tow placement with an on board thermal camera using the preheated substrate as a through transmission heat source. An investigation of the concept is conducted, and preliminary laboratory results are presented. Also included will be a brief overview of other emerging technologies that tackle the same issue. Keywords: Automated Fiber Placement, Manufacturing defects, Thermography

  13. Developing the information management system for safeguards national inspection

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. J.; Jeon, I.; Park, W. S.; Min, K. S. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    The inspection information management system for safeguards national inspection is aimed to do the national safeguards inspection with efficiency, and to decrease the inspector's load to write inspection report by systematizing the inspection jobs and sharing the inspection data. National safeguards inspection is consisted two large jobs. The first is the national safeguards supporting job of managing to support the national inspection mission. The other is the writing a national inspection report after completing the national inspection. Before the developing of inspection information management system, the official tools(spread sheet, word processor) are usually used. But there is problem to share the data, to produce the statistics data. To solve the these problem, we developed the inspection information management system that process the job from initial to final inspection work, and opened user education. This paper explain the procedure of developing the inspection information management system for safeguards national inspection.

  14. Pipe inspection using the pipe crawler. Innovative technology summary report

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) continually seeks safer and more cost-effective remediation technologies for use in the decontamination and decommissioning (D and D) of nuclear facilities. In several of the buildings at the Fernald Site, there is piping that was used to transport process materials. As the demolition of these buildings occur, disposal of this piping has become a costly issue. Currently, all process piping is cut into ten-foot or less sections, the ends of the piping are wrapped and taped to prevent the release of any potential contaminants into the air, and the piping is placed in roll off boxes for eventual repackaging and shipment to the Nevada Test Site (NTS) for disposal. Alternatives that allow for the onsite disposal of process piping are greatly desired due to the potential for dramatic savings in current offsite disposal costs. No means is currently employed to allow for the adequate inspection of the interior of piping, and consequently, process piping has been assumed to be internally contaminated and thus routinely disposed of at NTS. The BTX-II system incorporates a high-resolution micro color camera with lightheads, cabling, a monitor, and a video recorder. The complete probe is capable of inspecting pipes with an internal diameter (ID) as small as 1.4 inches. By using readily interchangeable lightheads, the same system is capable of inspecting piping up to 24 inches in ID. The original development of the BTX system was for inspection of boiler tubes and small diameter pipes for build-up, pitting, and corrosion. However, the system is well suited for inspecting the interior of most types of piping and other small, confined areas. The report describes the technology, its performance, uses, cost, regulatory and policy issues, and lessons learned

  15. Pipe inspection using the pipe crawler. Innovative technology summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The US Department of Energy (DOE) continually seeks safer and more cost-effective remediation technologies for use in the decontamination and decommissioning (D and D) of nuclear facilities. In several of the buildings at the Fernald Site, there is piping that was used to transport process materials. As the demolition of these buildings occur, disposal of this piping has become a costly issue. Currently, all process piping is cut into ten-foot or less sections, the ends of the piping are wrapped and taped to prevent the release of any potential contaminants into the air, and the piping is placed in roll off boxes for eventual repackaging and shipment to the Nevada Test Site (NTS) for disposal. Alternatives that allow for the onsite disposal of process piping are greatly desired due to the potential for dramatic savings in current offsite disposal costs. No means is currently employed to allow for the adequate inspection of the interior of piping, and consequently, process piping has been assumed to be internally contaminated and thus routinely disposed of at NTS. The BTX-II system incorporates a high-resolution micro color camera with lightheads, cabling, a monitor, and a video recorder. The complete probe is capable of inspecting pipes with an internal diameter (ID) as small as 1.4 inches. By using readily interchangeable lightheads, the same system is capable of inspecting piping up to 24 inches in ID. The original development of the BTX system was for inspection of boiler tubes and small diameter pipes for build-up, pitting, and corrosion. However, the system is well suited for inspecting the interior of most types of piping and other small, confined areas. The report describes the technology, its performance, uses, cost, regulatory and policy issues, and lessons learned.

  16. 40 CFR 63.695 - Inspection and monitoring requirements.

    Science.gov (United States)

    2010-07-01

    ...-permanently sealed (e.g., a welded joint between two sections of hard piping or a bolted and gasketed ducting... for compliance with the Tank Level 2 controls standards specified in § 63.685 of this subpart, the... not available, and specify a schedule of actions that will ensure that the control equipment will...

  17. 40 CFR 63.773 - Inspection and monitoring requirements.

    Science.gov (United States)

    2010-07-01

    ... according to the procedures of paragraph (c)(2)(iv) of this section. (i) For each closed-vent system joints, seams, or other connections that are permanently or semi-permanently sealed (e.g., a welded joint... using air emission controls in accordance with the requirements of §§ 63.765 and 63.766. (b) (c)...

  18. 40 CFR 63.1283 - Inspection and monitoring requirements.

    Science.gov (United States)

    2010-07-01

    ...) of this section. (i) For each closed-vent system joints, seams, or other connections that are permanently or semi-permanently sealed (e.g., a welded joint between two sections of hard piping or a bolted... using air emission controls in accordance with the requirements of § 63.1275. (b) (c) Closed-vent...

  19. 30 CFR 842.11 - Federal inspections and monitoring.

    Science.gov (United States)

    2010-07-01

    ... authority that is not arbitrary, capricious, or an abuse of discretion under the state program shall be... last two consecutive years, the rate at which adverse environmental or public health and safety... degree of stability of unreclaimed areas, taking into consideration the physical characteristics of...

  20. Bridging of inspection with corrosion management

    International Nuclear Information System (INIS)

    Formerly, Inspection and Corrosion Engineers have less interaction and sharing of information to each other even they are working in the same plant or organization. Inspection finding either from visual inspection or NDT techniques rarely shared with corrosion engineers. Similarly corrosion engineers rarely discussed their corrosion prediction and potential damage mechanism with inspection engineers. A demanding request of more holistic plant safety and asset integrity promoted the introduction and implementation of Risk Based Inspection (RBI). RBI analysis demands the input mainly from both disciplines i.e. Inspection and Corrosion Engineers. Most of RBI methodologies are once-off analysis approach which also promoted once-off interaction between Inspection and Corrosion Engineers. PETRONAS has developed a methodology with supporting software, integrating both Inspection and Corrosion disciplines. PETRONAS Risk Based Inspection (PRBI) is intended to promote continuous integration of Inspection and Corrosion management of the plant through out the whole life cycle starting from the design stage to fabrication, operation and decommissions stage. (author)

  1. Cognitive correlates of ultrasonic inspection performance

    International Nuclear Information System (INIS)

    This study provided a detailed examination of the thought processes required for conducting successful ultrasonic inspections of nuclear power plant components. When employed to detect or estimate the size of defects in components such as pipes and nozzles, an ultrasonic inspection can be a demanding cognitive task. A successful result requires the mental manipulation of a substantial amount of relevant information: knowledge about the component inspected, understanding of available ultrasonic techniques, and interpretation of an almost infinite variety of signal-characteristics obtained during the inspection. Reaching a correct conclusion from an inspection is a function of both the validity of the information obtained and the effectiveness with which the information is interpreted and weighed. Previous efforts to improve ultrasonic inspection performance have been directed mainly to the improvement of techniques and training for obtaining information. This study addressed improvement of the cognitive processes -- the mental manipulations required to reach a correct conclusion. The study was designed to learn what inspectors were doing and thinking while applying ultrasonic inspection techniques, and to relate key cognitive elements to inspection performance -- that is, to determine what aspects of these cognitive processes discriminate between effective and ineffective inspections. To this end, tape-recorded commentary was obtained and analyzed from 235 inspections of pipe-weld specimens. 26 refs., 39 figs

  2. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2012-06-21

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.

  3. A Robot Based Automatic Paint Inspection System

    Science.gov (United States)

    Atkinson, R. M.; Claridge, J. F.

    1988-06-01

    The final inspection of manufactured goods is a labour intensive activity. The use of human inspectors has a number of potential disadvantages; it can be expensive, the inspection standard applied is subjective and the inspection process can be slow compared with the production process. The use of automatic optical and electronic systems to perform the inspection task is now a growing practice but, in general, such systems have been applied to small components which are accurately presented. Recent advances in vision systems and robot control technology have made possible the installation of an automated paint inspection system at the Austin Rover Group's plant at Cowley, Oxford. The automatic inspection of painted car bodies is a particularly difficult problem, but one which has major benefits. The pass line of the car bodies is ill-determined, the surface to be inspected is of varying surface geometry and only a short time is available to inspect a large surface area. The benefits, however, are due to the consistent standard of inspection which should lead to lower levels of customer complaints and improved process feedback. The Austin Rover Group initiated the development of a system to fulfil this requirement. Three companies collaborated on the project; Austin Rover itself undertook the production line modifications required for body presentation, Sira Ltd developed the inspection cameras and signal processing system and Unimation (Europe) Ltd designed, supplied and programmed the robot system. Sira's development was supported by a grant from the Department of Trade and Industry.

  4. Steam generator tube inspection in Japan

    International Nuclear Information System (INIS)

    Steam generator tube inspection was first carried out in 1971 at Mihama Unit-1 that is first PWR plant in Japan, when the plant was brought into the first annual inspection. At that time, inspection was made on sampling basis, and only bobbin coil probe was used. After experiencing various kinds of tube degradations, inspection method was changed from sampling to all number of tubes, and various kinds of probes were used to get higher detectability of flaw. At present, it is required that all the tubes shall be inspected in their full length at each annual inspection using standard bobbin coil probe, and some special probes for certain plants that have susceptibility of occurrence of flaw. Sleeve repaired portion is included in this inspection. As a result of analyses of eddy current testing data, all indications that have been evaluated to be 20% wall thickness or deeper shall be repaired by either plugging or sleeving, where flaw morphology is to be a wastage or wear. Other types of flaw such as IGA/SCC are not allowed to be left inservice when those indications are detected. These inspections are performed according to inspection procedures that are approved by regulatory authority. Actual inspections are witnessed by the Japan Power engineering and inspection corporation (JAPEIC)'s inspectors during data acquisition and analysis, and they issue inspection report to authority for review and approval. It is achieved high safety performance of steam generator through this method of inspections, however. some tube leakage problems were experienced in the past. To prevent recurrence of such events, government is conducting development and verification test program for new eddy current testing technology

  5. Steam generator tube inspection in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Fukui, Shigetaka [Japan Power Engineering and Inspection Corp., Tokyo (Japan)

    1997-02-01

    Steam generator tube inspection was first carried out in 1971 at Mihama Unit-1 that is first PWR plant in Japan, when the plant was brought into the first annual inspection. At that time, inspection was made on sampling basis, and only bobbin coil probe was used. After experiencing various kinds of tube degradations, inspection method was changed from sampling to all number of tubes, and various kinds of probes were used to get higher detectability of flaw. At present, it is required that all the tubes shall be inspected in their full length at each annual inspection using standard bobbin coil probe, and some special probes for certain plants that have susceptibility of occurrence of flaw. Sleeve repaired portion is included in this inspection. As a result of analyses of eddy current testing data, all indications that have been evaluated to be 20% wall thickness or deeper shall be repaired by either plugging or sleeving, where flaw morphology is to be a wastage or wear. Other types of flaw such as IGA/SCC are not allowed to be left inservice when those indications are detected. These inspections are performed according to inspection procedures that are approved by regulatory authority. Actual inspections are witnessed by the Japan Power engineering and inspection corporation (JAPEIC)`s inspectors during data acquisition and analysis, and they issue inspection report to authority for review and approval. It is achieved high safety performance of steam generator through this method of inspections, however. some tube leakage problems were experienced in the past. To prevent recurrence of such events, government is conducting development and verification test program for new eddy current testing technology.

  6. Turbine rotors inspection problems associated with independent inspection

    International Nuclear Information System (INIS)

    As is well know, the serious problems affecting turbine-generator set rotors and moving parts, such as stress-corrosion cracking and/or the phenomena of creep/fatigue, have led the companies possessing these components to make considerable investments in terms of economy and human resources with a view to finding means for control and solutions. The fact that certain countries, such as Spain, have a limited number of fossil-fuelled and/or nuclear plants, with different suppliers and designs, means that the control and solving of such problems necessarily imply significant technological dependence and, consequently, that the resources used imply high associated costs that is most cases have to be paid in overseas currencies. This fact led several Spanish plant owners to propose that Tecnatom carry out an R ampersand D project aimed at developing and integral turbine rotor inspection and evaluation system designed to reduce technological dependence in this area through the application of in-house technology. This project identified as PC-850059 has been subsidized by the Spanish authorities through The Interministerial Commission of Science ampersand Technology. This article describes the developments achieved and the difficulties inherent to independent turbine rotor inspection and evaluation

  7. RPII Inspection and Licensing Activities and Annual Inspection Programme for 2013

    International Nuclear Information System (INIS)

    The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland RPII, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including inspection planning, the training of inspectors, the conduct of inspections as well as post inspection follow up and review. This report also provides an overview of the main features of the quality system

  8. Inspection, maintenance, and repair of large pumps and piping systems using advanced robotic tools

    International Nuclear Information System (INIS)

    Operating and maintaining large pumps and piping systems can be an expensive proposition. Proper inspections and monitoring can reduce costs. This was difficult in the past, since detailed pump inspections could only be performed by disassembly and many portions of piping systems are buried or covered with insulation. Once these components were disassembled, a majority of the cost was already incurred. At that point, expensive part replacement usually took place whether it was needed or not. With the completion of the Pipe Walkertrademark/LIP System and the planned development of the Submersible Walkertrademark, this situation is due to change. The specifications for these inspection and maintenance robots will ensure that. Their ability to traverse both horizontal and vertical, forward and backward, make them unique tools. They will open the door for some innovative approaches to inspection and maintenance of large pumps and piping systems

  9. Specificity of non destructive tests for the inspection of liquid metal cooled reactors

    International Nuclear Information System (INIS)

    In 2007, the French partners CEA, EDF and Areva have launched a coordinated research program for the development of Generation IV sodium-cooled fast reactors (SFR). The in-service inspection and repair capabilities were identified as major issues, concerning operation surveillance, periodical controls (normal and exceptional) and their associated robotic tools. Based on the return of experience gained with Rapsodie, Phenix and Superphenix reactors and EFR project, a pluri-annual R and D program was defined for ensuring, among other topics, the development of measurement and inspection techniques (continuous monitoring instrumentation and periodic inspection tools). The development of ultrasonic processes is taking a key place for tele-metering (position control of immersed structures in sodium), detection of structural defects (detection and sizing of cracks) and sodium en-gassing. Sensors have been developed to this end, as well as the associated inspection methods and specific developments of the CIVA software

  10. Visual Inspection for Caries Detection

    DEFF Research Database (Denmark)

    Gimenez, T; Piovesan, C; Braga, M M;

    2015-01-01

    We aimed to perform a systematic review including a meta-analysis to evaluate the overall accuracy of visual methods for detecting carious lesions and to identify possible sources of heterogeneity among the studies included. Two reviewers searched PubMed, Embase, Scopus, and other sources through...... July 2014 to identify published and nonpublished studies in English. Studies of visual inspection were included that 1) assessed accuracy of the method in detecting caries lesions; 2) were performed on occlusal, proximal, or free smooth surfaces in primary or permanent teeth; 3) had a reference...

  11. Quality Inspection of Printed Texts

    DEFF Research Database (Denmark)

    Pedersen, Jesper Ballisager; Nasrollahi, Kamal; Moeslund, Thomas B.

    2016-01-01

    -folded: for costumers of the printing and verification system, the overall grade used to verify if the text is of sufficient quality, while for printer's manufacturer, the detailed character/symbols grades and quality measurements are used for the improvement and optimization of the printing task. The......Inspecting the quality of printed texts has its own importance in many industrial applications. To do so, this paper proposes a grading system which evaluates the performance of the printing task using some quality measures for each character and symbols. The purpose of these grading system is two...

  12. Inspections in veterinary medicine 2005

    International Nuclear Information System (INIS)

    In Sweden 300 veterinary clinics have a license for x-ray diagnostics. Six of them also have a license for nuclear medicine. During 2005 eight clinics were inspected and the results show that the radiation protection in veterinary medicine can be improved. No clinic fulfilled the regulations of categorization of workplaces and workers (SSI FS 1998:3). Half of the clinics had no Swedish manual to the x-ray equipment and just as many had not performed the annual function check. Obviously, there is a need for more information to staff in veterinary medicine

  13. Instant Adobe Edge Inspect starter

    CERN Document Server

    Khan, Joseph

    2013-01-01

    Get to grips with a new technology, understand what it is and what it can do for you, and then get to work with the most important features and tasks. This easy-to-understand Starter guide will get you up to speed with Adobe Edge Inspect quickly and with little effort.This book is for frontend web developers and designers who are developing and testing web applications targeted for mobile browsers. It's assumed that you have a basic understanding of creating web applications using HTML, CSS, and JavaScript, as well as being familiar with running web pages from local HTTP servers. Readers are a

  14. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2008-01-01

    A basic assumption often made in risk- and reliability-based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a...... (and coalescence of small cracks) and increased crack growth. This should imply shorter inspection time intervals for ageing structures. Different approaches for updating inspection plans for older installations are proposed. The most promisingmethod consists of increasing the rate of crack initiations...... at the end of the expected lifetime - corresponding to a bath-tub hazard rate effect. The approach illustrated is for welded steel details in platforms. Systems effects are considered, including the use of dependence between inspection and failure events in different components for inspection...

  15. System for inspection of stacked cargo containers

    Science.gov (United States)

    Derenzo, Stephen

    2011-08-16

    The present invention relates to a system for inspection of stacked cargo containers. One embodiment of the invention generally comprises a plurality of stacked cargo containers arranged in rows or tiers, each container having a top, a bottom a first side, a second side, a front end, and a back end; a plurality of spacers arranged in rows or tiers; one or more mobile inspection devices for inspecting the cargo containers, wherein the one or more inspection devices are removeably disposed within the spacers, the inspection means configured to move through the spacers to detect radiation within the containers. The invented system can also be configured to inspect the cargo containers for a variety of other potentially hazardous materials including but not limited to explosive and chemical threats.

  16. Principles for National Inspections under IS Environment

    International Nuclear Information System (INIS)

    In 1997 the ROK introduced 'National Inspection' for nuclear material accountancy in its territory, and continues its independent verification activities besides the IAEA inspections. In 2004 the Additional Protocol was effectuated, and the IAEA finally decided to apply Integrated Safeguard to the ROK in 2008. This was a very significant milestone for Korea's nuclear transparency, which means that there are only nuclear activities with peaceful purposes and no more undeclared or suspicious nuclear activities. With this turning point, the previous inspection activities . IAEA and national inspections all together are to be adjusted to the new environment, i.e. Integrated Safeguards. Even for the SSAC, the objectives of national inspections are needed to be defined newly and its philosophy as well. In this paper, the principles of national inspections are suggested to address any verification challenges from the IS environment

  17. Inservice inspection of PFR secondary heat exchangers

    International Nuclear Information System (INIS)

    The author describes the current state of development to meet inservice inspection requirements of secondary heat exchangers of a prototype fast reactor: detection of defects in both the bore and outer surface of the tubes (pitting and cracking in the bore surface and fretting and thinning on the outer), full inspection of bends and straight portions, examination of the tube plate and of the tube/tube plate weld region. He reports the development of an eddy current probe for the in-service inspection (ISI) of the stainless steel tubing in the super-heater and re-heater, describes the influence of sodium concentration on eddy current inspection, and briefly evokes the detection of defects in bends. He describes the eddy current inspection of the evaporator tube bores, the wall thickness measurement in evaporator tubes. Then, he reports the in-service inspection of tube plates: tube bore examination, volumetric examination. He briefly discusses the obtained results

  18. Calculation of frequency of optimal inspection in non-notice inspection game

    International Nuclear Information System (INIS)

    We consider a non-notice inspection game between an inspection party, who verifies absence of diversion of nuclear materials and misuse of nuclear facility, and a facility operator, who tries them in a nuclear facility. In the game, the payoff for each player, inspection party and facility operator, is composed of various elements (parameters) such as facility type, a type of nuclear material, number of inspection and others. Their payoffs consist of profits and costs (minus profit). Because of random nature by non-notice inspection, its deterrence effect and inspection number could have the potential to affect their payoffs. In this paper, their payoffs taking into consideration of the inspection environment above are represented as a function of inspection number. Then, the optimal number is calculated from a condition on their payoffs for number of inspection. Comparable statics analysis is performed in order to observe the change of inspection number which is equilibrium point by changing these parameters including deterrence effect, because the number derived depends on each parameter within the inspection environment. Based on the analysis results, necessary conditions to reduce the inspection number keeping inspection effect are pointed out. (author)

  19. Upstream pipelines : inspection, corrosion and integrity management

    Energy Technology Data Exchange (ETDEWEB)

    Paez, J.; Stephenson, M. [Talisman Energy Inc., Calgary, AB (Canada)] (comps.)

    2009-07-01

    Accurate inspection techniques are needed to ensure the integrity of pipelines. This working group discussed methods of reducing pipeline failures for a variety of pipes. A summary of recent pipeline performance statistics was presented, as well as details of third party damage and fiberglass pipe failures. A batch inhibitor joint industry project was described. The session demonstrated that integrity program need to be developed at the field-level as well as at the upper management level. Fiberglass pipeline failures are significant problem for pipeline operators. Corrosion monitoring, pigging and specific budgets are needed in order to ensure the successful management of pipeline integrity. New software developed to predict pipeline corrosion rates was discussed, and methods of determining mole fractions and flow regimes were presented. The sessions included updates from regulators and standards agencies as well as discussions of best practices, regulations, codes and standards related to pipeline integrity. The working group was divided into 4 sessions: (1) updates since 2007 with input from the Canadian Association of Petroleum Producers (CAPP) and the Upstream Pipeline Integrity Management Association (UPIMA); (2) integrity of non-metallic pipelines; (3) upstream pipeline integrity issues; and (4) hot topics. tabs., figs.

  20. An explorative approach for inspecting Kepler data

    Science.gov (United States)

    Kügler, S. D.; Gianniotis, N.; Polsterer, K. L.

    2016-02-01

    The Kepler survey has provided a wealth of astrophysical knowledge by continuously monitoring over 150 000 stars. The resulting data base contains thousands of examples of known variability types and at least as many that cannot be classified yet. In order to reveal the knowledge hidden in the data base, we introduce a new visualization method that allows us to inspect regularly sampled time series in an explorative fashion. To that end, we propose dimensionality reduction on the parameters of a model capable of representing time series as fixed-length vector representation. We show that a more refined objective function can be chosen by minimizing the reconstruction error, that is the deviation between prediction and observation, of the observed time series instead of reconstructing model parameters. The proposed visualization exhibits a strong correlation between the variability behaviour of the light curves and their physical properties. As a consequence, temperature and surface gravity can, for some stars, be directly inferred from non- (or quasi-) periodic light curves.

  1. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-21

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2011 and includes inspection and repair activities completed at the following CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 453: Area 9 UXO Landfill (TTR); and (5) CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Appendix B. The inspection checklists are included in Appendix C, field notes are included in Appendix D, and photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted May 3 and 4, 2011. Maintenance was performed at CAU 424, CAU 453, and CAU 487. At CAU 424, two surface grade monuments at Landfill Cell A3-3 could not be located during the inspection. The two monuments were located and marked with lava rock on July 13, 2011. At CAU 453, there was evidence of animal burrowing. Animal burrows were backfilled on July 13, 2011. At CAU 487, one use restriction warning sign was missing, and wording was faded on the remaining signs. A large animal burrow was also present. The signs were replaced, and the animal burrow was backfilled on July 12, 2011. As a best management practice, the use restriction warning signs at CAU 407 were replaced with standard Federal Facility Agreement and Consent Order signs on July 13, 2011. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2011, and the vegetation monitoring report is included in Appendix F.

  2. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, For Calendar Year 2011

    International Nuclear Information System (INIS)

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2011 and includes inspection and repair activities completed at the following CAUs: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 407: Roller Coaster RadSafe Area (TTR); (3) CAU 424: Area 3 Landfill Complexes (TTR); (4) CAU 453: Area 9 UXO Landfill (TTR); and (5) CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports. The post-closure inspection plan for each CAU is included in Appendix B. The inspection checklists are included in Appendix C, field notes are included in Appendix D, and photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted May 3 and 4, 2011. Maintenance was performed at CAU 424, CAU 453, and CAU 487. At CAU 424, two surface grade monuments at Landfill Cell A3-3 could not be located during the inspection. The two monuments were located and marked with lava rock on July 13, 2011. At CAU 453, there was evidence of animal burrowing. Animal burrows were backfilled on July 13, 2011. At CAU 487, one use restriction warning sign was missing, and wording was faded on the remaining signs. A large animal burrow was also present. The signs were replaced, and the animal burrow was backfilled on July 12, 2011. As a best management practice, the use restriction warning signs at CAU 407 were replaced with standard Federal Facility Agreement and Consent Order signs on July 13, 2011. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2011, and the vegetation monitoring report is included in Appendix F.

  3. Post-Closure Inspection Letter Report for Corrective Action Unit 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2007-01-01

    This letter selves as the post closure monitoring letter report for the above CAU for the period October 2005 - September 2006. Quarterly inspections were conducted on December 12,2005, on March 23, 2006, on June 20,2006, and on September 19,2006, to observe the condition of the gate, use-restriction warning signs, monuments, fencing, trenches, soil covers, and monitoring well covers. The first inspection was conducted on December 12, 2005. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The second inspection was conducted on March 23, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The third inspection was conducted on June 20, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The fourth inspection was conducted on September 19, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended.

  4. Safety and Inspection Planning of Older Installations

    OpenAIRE

    Sørensen, John Dalsgaard; Ersdal, G.

    2008-01-01

    A basic assumption often made in risk- and reliability-based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no-crack detection assumption imply that the inspection time intervals usually become longer and longer with time. For ageing platforms several small cracks should be expected to be observed accordi...

  5. Remote ultrasonic inspection of Magnox reactor standpipes

    International Nuclear Information System (INIS)

    Although Magnox reactor standpipes are not subjected to routine in-service examination, it is occassionally necessary to inspect them for potential problems. Checks on wall thickness, weld integrity and the condition of inaccessible surfaces are made using remote ultrasonic immersion techniques from the bore. Special manipulators with rugged, inflatable seals allow the inspection zones to be completely flooded. The immersion technique has proved a reliable and safe method of inspection. Several of these applications are described. (author)

  6. AECL experience in fuel channel inspection

    International Nuclear Information System (INIS)

    Inspection of CANDU fuel channels (FC) is performed to ensure safe and economic reactor operation. CANDU reactor FCs have features that make them a unique non-destructive testing (NDT) challenge. The thin, 4 mm pressure-tube wall means flaws down to about 0.1 mm deep must be reliably detected and characterized. This is one to two orders of magnitude smaller than is usually considered of significant concern for steel piping and pressure vessels. A second unique feature is that inspection sensors must operate in the reactor core--often within 20 cm of highly radioactive fuel. Work on inspection of CANDU reactor FCs at AECL dates back over three decades. In that time, AECL staff have provided equipment and conducted or supervised in-service inspections in about 250 FCs, in addition to over 8000 pre-service FCs. These inspections took place at every existing CANDU reactor except those in India and Romania. Early FC inspections focussed on measurement of changes in dimensions (gauging) resulting from exposure to a combination of neutrons, stress and elevated temperature. Expansion of inspection activities to include volumetric inspection (for flaws) started in the mid-1970s with the discovery of delayed hydride cracking in Pickering 3 and 4 rolled joints. Recognition of other types of flaw mechanisms in the 1980s led to further expansion in both pre-service and in-service inspections. These growing requirements, to meet regulatory as well as economic needs, led to the development of a wide spectrum of inspection technology that now includes tests for hydrogen concentration, structural integrity of core components, flaws, and dimensional change. This paper reviews current CANDU reactor FC inspection requirements. The equipment and techniques developed to satisfy these requirements are also described. The paper concludes with a discussion of work in progress in AECL aimed at providing state-of-the-art FC inspection services. (author)

  7. Visual inspection. Better than your eyes

    International Nuclear Information System (INIS)

    Ongoing improvements in the development of camera technologies and manipulator techniques permit an enhanced performance of inspection tasks in nuclear services. In areas of reduced dose rate it's possible to use small size high resolution CCD cameras instead of tube cameras. Underwater inspections may be performed by submarine instead of rigid manipulator systems. This allows the enlargement of inspection areas and the performance at reduced time and personnel dose rate. (author)

  8. Periodic inspections of the primary system

    International Nuclear Information System (INIS)

    An impression is given of the inspection techniques, preparations and background for periodic examinations of the primary system of the Dodewaard Nuclear Reactor over the past 10 years. Unfortunately reliable integral inspection techniques to enable 'listening-in' to developing faults, are not yet available. Until they are, inspections will continue to be executed from a distance using different continuous methods, often under water and with a shortage of space and in the presence of ionising radiations. (C.F.)

  9. User interface inspection methods a user-centered design method

    CERN Document Server

    Wilson, Chauncey

    2014-01-01

    User Interface Inspection Methods succinctly covers five inspection methods: heuristic evaluation, perspective-based user interface inspection, cognitive walkthrough, pluralistic walkthrough, and formal usability inspections. Heuristic evaluation is perhaps the best-known inspection method, requiring a group of evaluators to review a product against a set of general principles. The perspective-based user interface inspection is based on the principle that different perspectives will find different problems in a user interface. In the related persona-based inspection, colleagues assume the

  10. China's coal export and inspection

    International Nuclear Information System (INIS)

    With the development of world's business and trade, coal has become a large part of the import and export goods in the international market. The total amount of coal trade has risen a lot. China is rich in coal resources. According to the estimate made by some experts, the reserve which has been explored recently could be exploited hundreds of years. China's output of raw coal has risen a lot during the past forty years. China coal industry has developed rapidly since the 1980s. It is possible for China to become a big coal export country since it has rich resources and increasing output. The paper suggests four steps which must be taken to expand coal exports in China: improve the level of management and administration of coal mines so as to raise the economic benefit; the follow-up production capacity of the present mines must be enhanced rapidly; step up construction of new large-scale mines; and China's coal washing capacity must be improved speedily since the low capacity has seriously influenced the improvement of coal quality. The paper describes the inspection bureaus and companies that have developed to perform inspection of exports in order to guarantee the quality of export coal

  11. Non-Destructive Inspection Lab (NDI)

    Data.gov (United States)

    Federal Laboratory Consortium — The NDI specializes in applied research, development and performance of nondestructive inspection procedures (flourescent penetrant, magnetic particle, ultrasonics,...

  12. Periodic and in-service inspection programs

    International Nuclear Information System (INIS)

    Periodic and in-service inspection programs for Cernavoda NPP consists of periodic inspections of CANDU NPP components CSAN N-285.4 and CSAN N-285.4, in-service inspections and repair and modifications general inspection. Periodic inspection program document (PIPD) determines the systems and components subject to inspection, the category of the inspection, techniques, areas and other details.The current status of the inspection programs is presented, including containment , erosion/corrosion, pressure vessel support and snubbers, main steam lines inspection programs. Qualification program in Cernavoda NPP involves equipment qualification in the on-site laboratory, yearly certification, special equipment qualification in the National Institute of Metrology. All procedures are approved by the ISCIR (regulatory body for pressure vessel and lifting equipment) and CNCAN (National Commission on Nuclear Activities Control). Qualification of the personnel is performed according to the ISCIR Technical prescription CR 11/82 for up to 3 year period. Final qualification and licensing is performed by CNCAN

  13. Computer vision technology in log volume inspection

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Log volume inspection is very important in forestry research and paper making engineering. This paper proposed a novel approach based on computer vision technology to cope with log volume inspection. The needed hardware system was analyzed and the details of the inspection algorithms were given. A fuzzy entropy based on image enhancement algorithm was presented for enhancing the image of the cross-section of log. In many practical applications the cross-section is often partially invisible, and this is the major obstacle for correct inspection. To solve this problem, a robust Hausdorff distance method was proposed to recover the whole cross-section. Experiment results showed that this method was efficient.

  14. Development of an automatic reactor inspection system

    International Nuclear Information System (INIS)

    Using recent technologies on a mobile robot computer science, we developed an automatic inspection system for weld lines of the reactor vessel. The ultrasonic inspection of the reactor pressure vessel is currently performed by commercialized robot manipulators. Since, however, the conventional fixed type robot manipulator is very huge, heavy and expensive, it needs long inspection time and is hard to handle and maintain. In order to resolve these problems, we developed a new automatic inspection system using a small mobile robot crawling on the vertical wall of the reactor vessel. According to our conceptual design, we developed the reactor inspection system including an underwater inspection robot, a laser position control subsystem, an ultrasonic data acquisition/analysis subsystem and a main control subsystem. We successfully carried out underwater experiments on the reactor vessel mockup, and real reactor ready for Ulchine nuclear power plant unit 6 at Dusan Heavy Industry in Korea. After this project, we have a plan to commercialize our inspection system. Using this system, we can expect much reduction of the inspection time, performance enhancement, automatic management of inspection history, etc. In the economic point of view, we can also expect import substitution more than 4 million dollars. The established essential technologies for intelligent control and automation are expected to be synthetically applied to the automation of similar systems in nuclear power plants

  15. Quality assurance for IAEA inspection planning

    International Nuclear Information System (INIS)

    Under the provisions of the Treaty on Nonproliferation of Nuclear Weapons and other agreements with states, the International Atomic Energy Agency (IAEA) conducts inspections at nuclear facilities to confirm that their operation is consistent with the peaceful use of nuclear material. The Department of Safeguards at the IAEA is considering a quality assurance program for activities related to the planning of these facility inspections. In this report, we summarize recent work in writing standards for planning inspections at the types of facilities inspected by the IAEA. The standards specify the sequence of steps in planning inspections, which are: (1) administrative functions, such as arrangements for visas and travel, and communications with the state to confirm facility operating schedules and the state's acceptance of the assigned inspectors; (2) technical functions including a specification of the required inspection activities, determination of personnel and equipment resources, and a schedule for implementing the inspection activities at the facility; and (3) management functions, such as pre- and post-inspection briefings, where the planned and implemented inspection activities are reviewed

  16. ENIQ: European Network for Inspection Qualification

    International Nuclear Information System (INIS)

    Many countries are currently considering their own approach to inspection qualification and are carefully assessing experience to date. ENIQ, which stands for European Network for Inspection Qualification, groups the major part of the utilities in Western Europe. The general objective of ENIQ is to coordinate and manage at European level expertise and resources for the assessment and qualification of NDE inspection techniques and procedures, primarily for nuclear components. Also non-nuclear heavy duty components will be considered. Within ENIQ there is a growing consensus of opinion on the general principles of a European approach towards inspection qualification. In this paper the main activities, organization and actual status of ENIQ will be discussed

  17. Optics damage inspection for the NIF

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, C. E., LLNL

    1998-06-01

    Two optics damage inspection systems will be implemented on the National Ignition Facility (NIF), one to inspect optics within the laser and transport sections and the other to inspect the final optics at the target chamber. Both systems use dark-field imaging technology to enhance resolution of defects. Details of each system design will be provided. A functional optics damage inspection system prototype, using dark-field imaging technology, is currently in operation on the Beamlet laser. This system provides us with the opportunity to measure non-ideal optical surfaces expected to be present on NIF. Prototype details and performance will be presented.

  18. Robotic inspection technology-process an toolbox

    Energy Technology Data Exchange (ETDEWEB)

    Hermes, Markus [ROSEN Group (United States). R and D Dept.

    2005-07-01

    Pipeline deterioration grows progressively with ultimate aging of pipeline systems (on-plot and cross country). This includes both, very localized corrosion as well as increasing failure probability due to fatigue cracking. Limiting regular inspecting activities to the 'scrapable' part of the pipelines only, will ultimately result into a pipeline system with questionable integrity. The confidence level in the integrity of these systems will drop below acceptance levels. Inspection of presently un-inspectable sections of the pipeline system becomes a must. This paper provides information on ROSEN's progress on the 'robotic inspection technology' project. The robotic inspection concept developed by ROSEN is based on a modular toolbox principle. This is mandatory. A universal 'all purpose' robot would not be reliable and efficient in resolving the postulated inspection task. A preparatory Quality Function Deployment (QFD) analysis is performed prior to the decision about the adequate robotic solution. This enhances the serviceability and efficiency of the provided technology. The word 'robotic' can be understood in its full meaning of Recognition - Strategy - Motion - Control. Cooperation of different individual systems with an established communication, e.g. utilizing Bluetooth technology, support the robustness of the ROSEN robotic inspection approach. Beside the navigation strategy, the inspection strategy is also part of the QFD process. Multiple inspection technologies combined on a single carrier or distributed across interacting container must be selected with a clear vision of the particular goal. (author)

  19. Managing aging in nuclear power plants: Insights from NRC's Maintenance Team Inspection reports

    International Nuclear Information System (INIS)

    A plant's maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified

  20. Camera Based 3D Mine-Shaft Inspection System

    OpenAIRE

    Wohlfeil, Jürgen; Spreckels, Volker; Strackenbrock, Bernhard; Schlienkamp, Andreas; Choinowski, André

    2015-01-01

    This paper describes the development of an Optical 3D Shaft Inspection System needed for the survey and monitoring of Water Handling Shafts in the German Ruhrgebiet. The development is part of the RAG R&D project “ABSMon”. The end of the German hard coal mining at the end of 2018 has been determined with the Steinkohlefinanzierungsgesetz (SteinkohleFinG) from 2007-12-20. About three hundred years before now the near surface hard coal mining began in the southern Ruhr Area an...

  1. 9 CFR 77.37 - Interstate movement from monitored herds.

    Science.gov (United States)

    2010-01-01

    ... number of slaughter inspections or negative testing captive cervids reported in any given year must be at... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Interstate movement from monitored herds. 77.37 Section 77.37 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION...

  2. The interactive on-site inspection system: An information management system to support arms control inspections

    Energy Technology Data Exchange (ETDEWEB)

    DeLand, S.M.; Widney, T.W.; Horak, K.E.; Caudell, R.B.; Grose, E.M.

    1996-12-01

    The increasing use of on-site inspection (OSI) to meet the nation`s obligations with recently signed treaties requires the nation to manage a variety of inspection requirements. This document describes a prototype automated system to assist in the preparation and management of these inspections.

  3. Optimized inspection techniques and structural analysis in lifetime management

    International Nuclear Information System (INIS)

    Preservation of the option of extending the service lifetime of a nuclear power plant beyond its normal design lifetime requires correct remaining lifetime management from the very beginning of plant operation. The methodology used in plant remaining lifetime management is essentially based on the use of standard inspections, surveillance and monitoring programs and calculations, such as thermal-stress and fracture mechanics analysis. The inspection techniques should be continuously optimized, in order to be able to detect and dimension existing defects with the highest possible degree of accuracy. The information obtained during the inspection is combined with the historical data of the components: design, quality, operation, maintenance, and transients, and with the results of destructive testing, fracture mechanics and thermal fatigue analysis. These data are used to estimate the remaining lifetime of nuclear power plant components, systems and structures with the highest degree possible of accuracy. The use of this methodology allows component repairs and replacements to be reduced or avoided and increases the safety levels and availability of the nuclear power plant. Use of this strategy avoids the need for heavy investments at the end of the licensing period

  4. Application of risk based inspection as a part of life management of nuclear power plants

    International Nuclear Information System (INIS)

    Full text: Risk Informed approach is a systematic effort to improve plant safety in a more efficient manner by distributing the available safety resources depending on the importance to plant safety. This approach has found immense application in various aspects associated with Nuclear Power Plants, including design, manufacturing, operation and regulation. Typical applications of Risk Informed approach are in Technical Specification, In-Service Inspection (ISI) requirements, Motor Operated Valve testing, Configuration Control etc. In order to cater to such variety of Probabilistic Safety Assessment (PSA) based Risk Informed requirements, a software package, 'Risk Monitor' has been developed by the authors. An important application of Risk informed approach that has been undertaken for Indian Pressurised Heavy Water Reactor (IPHWR) is towards Risk Informed In-Service Inspection (RI-ISI). Studies are being conducted to evolve an inspection plan that is optimised to provide effective inspections at the right location with a proper inspection frequency. Using risk informed approach, the identification of system / component for inspection resource allocation is based on the results from Level 1 PSA of a NPP. Even though this methodology can be employed on any of the nuclear components/systems such as mechanical systems, instrumentation, etc., as a starting point, piping has been considered for employing Risk Informed Inspection. Plant risk assessment is modelled through the analysis of Core Damage Frequency (CDF) using PSA models. Risk Informed Inspection program of piping involves the estimation of failure probability or frequency of a piping segment and estimation of consequences of piping failures. ISI program changes could affect the failure probability values of piping and can introduce a change in CDF. These effects can be brought out through the implementation of Risk Informed inspection strategy. Various importance measures like Fussel-Vesely, Birnbaum

  5. Area 2 Bitcutter and Post-Shot Injection Wells: Corrective Action Unit 90 Post-Closure Inspection Annual Report; TOPICAL

    International Nuclear Information System (INIS)

    Area 2 Bitcutter and Post-Shot Containment Shop Injection Wells Corrective Action Unit (CAU) 90 Post-Closure Monitoring requirements are described in section V.B.8.b of the Nevada Test Site Resource Conservation and Recovery Act Permit for a Hazardous Waste Management Facility No. NEV HW009, modified May 31, 1997, Revision 3. Post-closure care consists of the following: Semiannual inspections of the unit using an inspection checklist; Photographic documentation; Field note documentation; and Preparation and submittal of an annual report. The report includes copies of the inspection checklist, photographs, and recommendations and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and a copy of the inspection photographs is found in Attachment C

  6. International conference on maintenance, inspection, corrosion, materials, engineering and plant reliability: technical volume

    International Nuclear Information System (INIS)

    This technical volume contains articles based on MICMEP-99 in the fields of process plant operation, maintenance, inspection, non-destructive testing, condition monitoring, engineering consultancy etc., the vendors for engineering items, equipment fabrication, welding consumables, ceramic and insulation lining, coating, painting etc. Papers relevant to INIS are indexed separately

  7. In-service inspection of process instruments and reactivity control mechanisms

    International Nuclear Information System (INIS)

    Nuclear research reactors, like any other operating process plant, employ a large number of instruments for monitoring process parameters. Besides monitoring the parameters, these instruments also protect the primary systems against unacceptable deviations and activate safety devices. In reactors where the power regulation is performed by varying the moderator level, closed loop instrumentation systems are used. In-service inspection and Preventive maintenance programs are established with respect to structures, systems and components important to safety of nuclear reactors

  8. 49 CFR 230.32 - Time and method of inspection.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Time and method of inspection. 230.32 Section 230... Appurtenances Inspection and Repair § 230.32 Time and method of inspection. (a) Time of inspection. The entire... other components interfering with the provision of inspection access shall be removed at this...

  9. 46 CFR 160.064-6 - Examinations, tests and inspections.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 6 2010-10-01 2010-10-01 false Examinations, tests and inspections. 160.064-6 Section... Examinations, tests and inspections. (a) Manufacturer's inspection and tests. Manufacturers of listed and... upon request. (b) Laboratory inspections and tests. Such examinations, inspections and tests as...

  10. 46 CFR 164.012-13 - Examinations, tests, and inspections.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 6 2010-10-01 2010-10-01 false Examinations, tests, and inspections. 164.012-13 Section...-13 Examinations, tests, and inspections. (a) Manufacturer's inspection and tests. Manufacturers of... upon request. (b) Laboratory inspection and tests. Such examinations, inspections and tests as...

  11. Ultrasonic inspection of austenitic welds

    International Nuclear Information System (INIS)

    The ultrasonic examination of austenitic stainless steel weld metal has always been regarded as a difficult proposition because of the large and variable ultrasonic attenuations and back scattering obtained from apparently similar weld deposits. The work to be described shows how the existence of a fibre texture within each weld deposit (as a result of epitaxial growth through successive weld beads) produces a systematic variation in the ultrasonic attenuation coefficient and the velocity of sound, depending upon the angle between the ultrasonic beam and the fibre axis. Development work has shown that it is possible to adjust the welding parameters to ensure that the crystallographic texture within each weld is compatible with improved ultrasonic transmission. The application of the results to the inspection of a specific weld in type 316 weld metal is described

  12. Inspection of PFR steam generators

    International Nuclear Information System (INIS)

    The inspection of PFR evaporator tubing, superheater and reheater tubing, and tube plate examinations, are described. Ferritic steel U tubes in the evaporator have been examined by an eddy current system operating at 400 kHz using flexible rotating probes. Surface defects as shallow as 0.1 mm can be detected and sized in the range 0.1 to 0.5 mm deep. An ultrasonic method is under development for wall thickness. Special test coil probes have been developed for examination of the type 316 stainless steel superheater and reheater tubing. Crack-life defects in the bore are detectable at approximately 10% wall thickness and 20% on the outside diameter. Tube plate examinations from the tube holes, have been conducted using eddy current probes which identify surface breaking cracks in the holes. For detecting curtain cracks between tube plate holes, ultrasonic compression wave probes have been used. (U.K.)

  13. Working session 2: Tubing inspection

    Energy Technology Data Exchange (ETDEWEB)

    Guerra, J. [Tecnatom, S.A. San Sebastian de los Reyes, Madrid (Spain); Tapping, R.L. [AECL, Chalk River, Ontario (Canada)

    1997-02-01

    This session was attended by delegates from 10 countries, and four papers were presented. A wide range of issues was tabled for discussion. Realizing that there was limited time available for more detailed discussion, three topics were chosen for the more detailed discussion: circumferential cracking, performance demonstration (to focus on POD and sizing), and limits of methods. Two other subsessions were organized: one dealt with some challenges related to the robustness of current inspection methods, especially with respect to leaving cracked tubes in service, and the other with developing a chart of current NDE technology with recommendations for future development. These three areas are summarized in turn, along with conclusions and/or recommendations. During the discussions there were four presentations. There were two (Canada, Japan) on eddy current probe developments, both of which addressed multiarray probes that would detect a range of flaws, one (Spain) on circumferential crack detection, and one (JRC, Petten) on the recent PISC III results.

  14. Laser Damage Inspection Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Salmon, J T; Brase, J M; Bliss, E S; Carrano, C J; Kegelmeyer, L M; Miller, M G; Orth, C D; Sacks, R A

    2001-02-26

    Large, high-power laser systems are often designed as reimaging multipass cavities to maximize the extraction of energy from the amplifiers. These multipass cavities often have vacuum spatial filters that suppress the growth of beam instability via B-integral effects. These spatial filters also relay images of laser damage, often nearly superimposing these images in common planes. Also, the fluence damage threshold limits the minimum size of the optics. When used as vacuum barriers in the spatial filters, these large optics present a safety hazard from the risk of implosion if the laser damage were sufficiently large. The objective of the project was to develop algorithms and methods for optical detection and characterization of laser-induced damage of optics. The system should detect small defects (about 5% of the critical size), track their growth over multiple laser shots, and characterize the defects accurately so that the optic can be replaced (at 25% of the critical size) and, hence, minimize the risk of implosion. The depth of field must be short enough to isolate the damaged vacuum barrier from other damaged optics in the beamline, and the system should also be capable of inspecting other optics in the beamline, since damage on one optic can subsequently damage subsequent optics. Laser induced damage starts as a small (<<1mm) crater and grows as material is removed on subsequent laser shots. The highly fractured rough surface of the crater scatters light from the illuminating inspection beam. This scattered light is imaged by the inspection system. Other types of defects may occur as well including inclusions in the bulk glass, tooling marks, and surface contamination. This report will discuss the detection and characterization of crater-like surface defects although the general techniques may prove useful for other types of defects. The work described here covers the development of an image processing approach and specific algorithms for defect detection

  15. Apparatus for inspecting failed fuel

    International Nuclear Information System (INIS)

    Object: To provide electrode rods on an inner surface of a shipper cap and pressure detectors in the form of microswitches on four sides of the outer surface thereof to positively set the shipper cap to the channel and to positively separate reactor water within the channel from ambient reactor water. Structure: When the shipper cap is set on the channel, the four sides of the cap come into contact with a grid plate to upwardly move each rod against a return spring, and each microswitch is actuated through contact to light the indicating lamp, after which air is fed into the shipper cap to move a water level of reactor water within the channel from the electrode, thus separating from the ambient reactor water for subsequent operation for inspecting failed fuel. (Kamimura, M.)

  16. Modifications to the INSPECT model

    Energy Technology Data Exchange (ETDEWEB)

    Dickinson, S. [AEA Technology, Winfrith (United Kingdom); Sims, H.E. [AEA Technology, Harwell (United Kingdom)

    1996-12-01

    The prediction of iodine behaviour in the containment of a PWR following a loss of coolant accident requires a reliable model of the chemistry of iodine in aqueous solution. The INSPECT model, which was developed several years ago, contains a large number of the relevant chemical reactions of iodine and water radiation chemistry. Since the reactions set was first assembled, however, new data on rate constants and mechanisms have become available. In addition, the application of the model to various small-scale experiments has revealed problems in the modelling of some reactions, leading to an under-prediction of the iodine volatility at high pH, although the experiments have demonstrated that the high pH volatility remains satisfactory low. This paper describes the modifications which have been made to the INSPECT model to take account of new data and to improve the modelling where appropriate. The main changes which have been made to the reaction set are as follows: - The rate constants and activation energies for the reactions describing the radiolysis of water have been updated in with recent assessments, and the temperature dependence of the G value for the primary species have been accordance taken into account, - The mechanism and rates of I{sub 2} hydrolysis have been modified in accordance with the latest assessments of this reaction, - The mechanism for the reaction of I{sub 2} with H{sub 2}O{sub 2} has been changed to a form which produces a more realistic pH dependence under neutral and alkaline conditions, - An addition mechanism for the disproportionation of the O{sub 2} ion has been included, reflecting experimental observations that this reaction has a significant first-order component under all but the purest conditions, - Atomic I is treated as a volatile species, with a partition coefficient of 1.9 at 298 K. (Abstract Truncated)

  17. Cost-effective inspection qualification

    International Nuclear Information System (INIS)

    Non destructive testing (NDT) is now recognized as an essential element in the safe operation of all kinds of industrial plant. By demonstrating that defects of a size sufficient to threaten structural integrity are absent both prior to operation and at intervals during service, NDT gives assurance that the plant is safe to operate. Regulatory bodies in many of the countries operating nuclear plant have introduced a requirement for some form of performance demonstration. The responsibility for the nature and detail of the inspection is entirely with the plant owner who is free to use whatever methods he judges appropriate. However, there must then be a demonstration that the method chosen is capable of meeting the demands placed on it by the safety case. The precise requirements for performance demonstration vary from country to country. There are variations in the degree of independence required as well as in the precise way that the demonstration is performed. Such variations have proved to have a highly significant effect on both the cost and time requirements of performance demonstration and on the degree of confidence in the NDT arising from the process. The Inspection Validation Centre in the UK was established by AEA Technology to carry out the performance demonstration work for Sizewell B. It has also been involved in implementing both the ASME XI and ENIQ approaches. This paper examines the three approaches to performance demonstration from this standpoint of practical experience and draws conclusions about the cost, difficulty and effectiveness of each. Section 2 describes the validation activities for Sizewell B, Section 3 the ASME requirements and Section 4 the ENIQ qualification methods. Finally, Section 5 compares the three systems and contains the conclusions arising from this comparison

  18. Study on in-vessel ISI for JOYO. Laser based ultra sonic non-destructive inspection and manipulation technique

    International Nuclear Information System (INIS)

    This report describes the feasibility study on the in-vessel inspection technique to be applied for the experimental fast reactor JOYO. Since JOYO is a sodium cooled fast reactor and the core structure components are in high temperature and fast neutron irradiation environment, material strength yields to decrease due to heat fatigue and irradiation induced embrittlement. The present surveillance method of testing structural material mechanical property, monitoring subassembly outlet temperature and sodium leak monitoring are not sufficient to detect abnormalities with a small crack. Therefore, the direct inspection method to confirm the core structure integrity needs to be developed considering the recent innovative technology. Since the core structure has a complicated form and components under sodium are not visible, the manipulator technology is essential which has various positioning functions. The core support plate was selected to be an important inspection item, and the method which combines ultrasonic non-destructive inspection technology and manipulator technology was examined. As a result, the concept of core support plate inspection equipment under sodium condition was obtained by contacting ultrasonic sensor from inner side of the core support plate. Another concept was examined by applying laser based ultrasonic inspection technology. This method has advantage of remote control operation because of no-contacting inspection and it was confirmed to be feasible for JOYO in-vessel inspection method from viewpoint of defective detection accuracy and laser transmission ability by means of fiber cable. This is promising for in-vessel inspection without sodium draining. Based on this study, the development of in-vessel inspection equipment is continued and the proto-type will be demonstrated in JOYO. (author)

  19. Developing inspection strategies to support local activities

    DEFF Research Database (Denmark)

    Jensen, Per Langå

    2003-01-01

    An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection.......An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection....

  20. 75 FR 42643 - National Tunnel Inspection Standards

    Science.gov (United States)

    2010-07-22

    ... Advance Notice of Proposed Rulemaking (ANPRM) The FHWA issued an ANPRM on November 18, 2008, at 73 FR... vulnerability to the tunnel operating environment and mean time to failure. The ACEC commented that inspection... Federal Highway Administration 23 CFR Part 650 RIN 2125-AF24 National Tunnel Inspection Standards...

  1. 7 CFR 982.446 - Inspection documentation.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Inspection documentation. 982.446 Section 982.446 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing... WASHINGTON Administrative Rules and Regulations § 982.446 Inspection documentation. Pursuant to §...

  2. Handling and inspection of nuclear fuel elements

    International Nuclear Information System (INIS)

    The invention provides improvements in the handling and inspection of nuclear fuel elements. A mobile bridge is mounted astraddle over a water tank, and from said bridge is suspended and immersed insulating plate capable of vertically receiving a fuel element and of taking a horizontal position for inspecting the latter. This can be applied to nuclear power stations

  3. Annual Radioactive Waste Tank Inspection Program - 1997

    International Nuclear Information System (INIS)

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1997 to evaluate these vessels, and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

  4. 49 CFR 177.802 - Inspection.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Inspection. 177.802 Section 177.802 Transportation Other Regulations Relating to Transportation PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION... and Regulations § 177.802 Inspection. Records, equipment, packagings and containers under the...

  5. An intelligent inspection and survey robot

    International Nuclear Information System (INIS)

    ARIES (Autonomous Robotic Inspection Experimental System) is a semi-autonomous robotic system intended for use in the automatic inspection of stored containers of low-level nuclear waste. This article describes the technology and how it could be used. 3 refs., 3 figs

  6. Annual Radioactive Waste Tank Inspection Program - 1998

    Energy Technology Data Exchange (ETDEWEB)

    McNatt, F.G.

    1999-10-27

    Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Inspections made during 1998 to evaluate these vessels and auxiliary appurtenances, along with evaluations based on data accrued by inspections performed since the tanks were constructed, are the subject of this report.

  7. 9 CFR 146.11 - Inspections.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Inspections. 146.11 Section 146.11 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE... premises will be conducted if a State Inspector determines that a breach of testing has occurred for...

  8. 9 CFR 145.12 - Inspections.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Inspections. 145.12 Section 145.12 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE..., “Flock Selecting and Testing Report”; VS Form 9-3, “Report of Sales of Hatching Eggs, Chicks, and...

  9. Ultrasonic Inspection Of Welds On Tube Fittings

    Science.gov (United States)

    Ray, Arjun N.; Nummelin, John L.

    1996-01-01

    Scanning ultrasonic apparatus designed for use in nondestructive inspection of electron-beam welds between heat-exchanger tube and end fittings. Includes ultrasonic probe, scanning mechanism, ultrasonic-signal-generating and -processing circuits, and computers. Not necessary to immerse any part of apparatus or tube/fitting assembly in water during inspection. Output ultrasonic-test signals displayed on computer to reveal defects.

  10. Automatic visual inspection of hybrid microcircuits

    Energy Technology Data Exchange (ETDEWEB)

    Hines, R.E.

    1980-05-01

    An automatic visual inspection system using a minicomputer and a video digitizer was developed for inspecting hybrid microcircuits (HMC) and thin-film networks (TFN). The system performed well in detecting missing components on HMCs and reduced the testing time for each HMC by 75%.

  11. Ultrasound periodic inspections of reactor pressure vessels

    International Nuclear Information System (INIS)

    Two versions are described of ultrasonic equipment for periodic inspections of reactor pressure vessels. One uses the principle of exchangeable programmators with solid-state logic while the other uses programmable logic with semiconductor memories. The equipment is to be used for inspections of welded joints on the upper part of the V-1 reactor pressure vessel. (L.O.)

  12. Inspection of nuclear fuel transport in Spain

    International Nuclear Information System (INIS)

    The experience acquired in inspecting nuclear fuel shipments carried out in Spain will serve as a basis for establishing the regulations wich must be adhered to for future transports, as the transport of nuclear fuels in Spain will increase considerably within the next years as a result of the Spanish nuclear program. The experience acquired in nuclear fuel transport inspection is described. (author)

  13. Inspections talks with IAEA again broken off

    International Nuclear Information System (INIS)

    North Korea again appears likely to resist more detailed safeguards inspections of its disputed nuclear facilities by the International Atomic Energy Agency. The country's loner status was reinforced during the IAEA General Conference in September, when no other nation joined North Korea in voting against the placement of the inspection issue on the conference's agenda

  14. A web environment for inspection service

    International Nuclear Information System (INIS)

    The in-service inspection fundamental objective is to maintain the structural integrity of structures, systems and components during the life in the installation service. Nuclear power plants are required to implement a Service inspection program in accordance with the established regulation by the Regulatory body.

  15. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2009-06-11

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

  16. Inservice inspection of Halden BWR pressure vessel

    International Nuclear Information System (INIS)

    A description is given of how the recertification inspection of the 20 years old Halden Reactor pressure vessel was carried out in accordance with the latest ASME-CODES, despite the fact that inspection accessibility was poor. As no volumetric inspection had been carried out since the preservice radiography in 1957, the ultrasonic inspection included the high flux region of all welds. In total 70% of longitudinal welds and 20% of bottom circumferential welds were inspected as well as the bottom nozzle connection. The vessel was not designed with provisions for inservice inspection, the welds are unaccessible from the outside and removal of the lid is virtually impossible. The ultrasonic probes could only be loaded through 77 mm diameter holes in the top lid and remotely positioned inside the vessel. The inspection was performed using 450C and 60OC 1 MHz angle probes and 2.25 MHz normal probes in immersion technique. In a zone around the welds, small regions with lack of bonding between the stainless steel cladding and the boiler steel were revealed. One root defect known and accepted from the preservice radiographs was examined. The defect was found to be 6x30mm as a maximum and well within acceptable limits according to the fracture mechanics analysis method recommended in ASME X1. The inspection required a period of three weeks' work in the reactor hall. (UK)

  17. Underground pipe inspection device and method

    Science.gov (United States)

    Germata, Daniel Thomas

    2009-02-24

    A method and apparatus for inspecting the walls of an underground pipe from inside the pipe in which an inspection apparatus having a circular planar platform having a plurality of lever arms having one end pivotably attached to one side of the platform, having a pipe inspection device connected to an opposite end, and having a system for pivoting the lever arms is inserted into the underground pipe, with the inspection apparatus oriented with the planar platform disposed perpendicular to the pipe axis. The plurality of lever arms are pivoted toward the inside wall of the pipe, contacting the inside wall with each inspection device as the apparatus is conveyed along a length of the underground pipe.

  18. Design inspections for systems undergoing design modifications

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's (NRC's) Office of Inspection and Enforcement (IE) has conducted direct inspections (integrated design inspections) of the technical aspects of the nuclear plant design process for several plants under construction. It has also evaluated independent design verification programs and engineering assurance programs at a number of other plants under construction. Many of the lessons learned from these construction phase efforts are directly applicable to operating plants undergoing major modifications. This has been confirmed by IE direct inspections of the design aspects of safety systems outage modifications, which have identified significant potential safety-related deficiencies. The paper discusses methodology for design inspections; failure to maintain up-to-date design basis documentation; and lessons learned common to plants under construction and undergoing major modifications

  19. Inspection of Candu Nuclear Reactor Fuel Channels

    International Nuclear Information System (INIS)

    The Channel Inspection and Gauging Apparatus of Reactors (CIGAR) is a fully atomated, remotely operated inspection system designed to perform multi-channel, multi-task inspection of CANDU reactor fuel channels. Ultrasonic techniques are used for flaw detection, (with a sensitivity capable of detecting a 0.075 mm deep notch with a signal to noise ratio of 10 dB) and pressure tube wall thickness and diameter measurements. Eddy currrent systems are used to detect the presence of spacers between the coaxial pressure tube and calandria tube, as well as to measure their relative spacing. A servo-accelerometer is used to estimate the sag of the fuel channels. This advanced inspection system was commissioned and declared in service in September 1985. The paper describes the inspection systems themselves and discussed the results achieved to-date. (author)

  20. Licensee contractor and vendor inspection status report

    International Nuclear Information System (INIS)

    A fundamental premise of the Nuclear Regulatory Commission's (NRC) licensing and inspection program is that licensees are responsible for the proper construction and safe and efficient operation of their nuclear power plants. The total government-industry system for the inspection of commercial nuclear facilities has been designed to provide for multiple levels of inspection and verification. Licensees, contractors, and vendors each participate in a quality verification process in compliance with requirements prescribed by the NRC's rules and regulations (Title 10 Code of Federal Regulations). The NRC performs an overview of the commercial nuclear industry by inspection to determine whether its requirements are being met by licensees and their contractors, while the major inspection effort is performed by the industry within the framework of ongoing quality verification programs

  1. Sipping inspection method for fuel assembly

    International Nuclear Information System (INIS)

    Purpose: To shorten the periodical inspection time required for sipping inspection (failed fuel inspection) in PWR type reactors or the likes by mounting a plurality of a fuel assemblies in a sipping can to thereby inspect the plurality of fuel assemblies simultaneously. Method: Upon sipping inspection of fuels temporarily stored in a spent fuel storage pool, a plurality of fuel assemblies are mounted in a sipping can. Then, after placing a cover, N2 gases are caused to flow as carrier gas from a gas container by the operation to valves. Then, N2 gases are circulated by a jet pump and water in the can is sucked by a water pump. A radioactivity detector such as a scintillation counter is provied to a part of the loop for measuring the amount of the radioactivity in the portion where water is passed to check whether leakage is present or not. (Horiuchi, T.)

  2. Cognitive functioning in newly presenting patients with supratentorial intracranial tumors: is there a role for inspection time?

    OpenAIRE

    Scotland, Jennifer L; Whittle, Ian R; Deary, Ian J

    2012-01-01

    Quantifying the extent of cognitive dysfunction in patients with intracranial tumors is important to monitor treatment effects and assess patients' needs. Inspection time, a measure of the efficiency of visual information processing, was evaluated, and its usefulness in patients with intracranial tumors was compared with that of other widely used cognitive tests. Newly presenting inpatients with supratentorial intracranial tumors (n = 118) underwent preoperative assessment using inspection ti...

  3. Virginia Tech Goldwater scholars have high goals as bio-researchers

    OpenAIRE

    Crumbley, Liz

    2004-01-01

    Two Virginia Tech students have won highly competitive Barry M. Goldwater scholarships for the 2004-2005 academic year and intend to play active roles in the future of bionics and biochemistry research.

  4. POST-CLOSURE INSPECTION REPORT FOR THE TONOPAH TEST RANGE, NEVADA, FOR CALENDAR YEAR 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-04-01

    This Post-Closure Inspection Report provides an analysis and summary of the semi-annual inspections conducted at the Tonopah Test Range (TTR) during Calendar Year 2004. The report includes the inspection and/or repair activities completed at the following nine Corrective Action Units (CAUs) located at TTR, Nevada: (1) CAU 400: Bomblet Pit and Five Points Landfill (TTR); (2) CAU 404: Roller Coaster Lagoons and Trench (TTR); (3) CAU 407: Roller Coaster RadSafe Area (TTR); (4) CAU 423: Area 3 Underground Discharge Point, Building 0360 (TTR) (5) CAU 424: Area 3 Landfill Complexes (TTR); (6) CAU 426: Cactus Spring Waste Trenches (TTR); (7) CAU 427: Area 3 Septic Waste Systems 2,6 (TTR); (8) CAU 453: Area 9 UXO Landfill (TTR); and (9) CAU 487: Thunderwell Site (TTR). Site inspections were conducted on July 7,2004, and November 9-10,2004. All inspections were conducted according to the post-closure plans in the approved Closure Reports (CRs). The post-closure inspection plan for each CAU is included in Appendix B, with the exception of CAU 400 and CAU 423. CAU 400 does not require post-closure inspections, but inspections of the vegetation and fencing are conducted as a best management practice. In addition, post-closure inspections are not currently required at CAU 423; however, the CR is being revised to include inspection requirements. The inspection checklists for each site inspection are included in Appendix C, the field notes are included in Appendix D, and the site photographs are included in Appendix E. Vegetation monitoring of CAU 400, CAU 404, CAU 407, and CAU 426 was performed in June 2004, and the vegetation monitoring report is included in Appendix F. In addition, topographic survey results of two repaired landfill cells in CAU 424 are included in Appendix G. Maintenance and/or repairs were performed at the CAU 400 Five Points Landfill, CAU 407, CAU 424, CAU 427, and CAU 487. CAU 400 repairs included mending the fence, reseeding of a flood damaged area, and

  5. Ultrasonic inspection of complex geometry components for the Sizewell B pre-service inspections

    International Nuclear Information System (INIS)

    Sizewell B, the first British PWR, is nearing completion and the primary and secondary circuits are undergoing extensive pre-service inspection. OIS is carrying out the inspection of the Incredibility Of Failure (IOF) and Class 1 components. These are nearly all automated inspections and many of the components are austenitic. The NDT Applications Centre of Nuclear Electric has provided its MIPS and GUIDE automated ultrasonic inspection software systems for these inspections. The high quality of inspection required for Sizewell B has required the development of novel manipulators, particularly for the complex geometry components such as the 45o branch nozzle, to enable the necessary ultrasonic coverage to be achieved. Some of these manipulators have four axes of motion and the MIPS software has been enhanced to enable the required complex scan patterns to be achieved. The precise plotting of ultrasonic data provided by MIPS and GUIDE has enabled the methods successfully deployed by Nuclear Electric during the PISC II trials to be implemented for these site inspections. Many of the inspections are subject to independent validation by the Inspection Validation Centre operated by AEA Technology. This paper describes the inspection system developments which have been undertaken and reviews the experience to date in performing these inspections. (Author)

  6. Global Monitoring

    OpenAIRE

    Victor Ya. Tsvetkov

    2012-01-01

    The article describes the technology and classification of global monitoring, shows the relationship between the global monitoring and geographic information monitoring, presents the cause-and-effect diagram of global monitoring. The paper discloses the value of the time series for global monitoring, offers a functional diagram of the global monitoring system, gives the main characteristics of global monitoring.

  7. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2009

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2010-06-21

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2009 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2009 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per LWO-LWE-2008-00423, HLW Tank Farm Inspection Plan for 2009, were completed. All Ultrasonic measurements (UT) performed in 2009 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 1, and WSRC-TR-2002-00061, Rev.4. UT inspections were performed on Tank 29 and the findings are documented in SRNL-STI-2009-00559, Tank Inspection NDE Results for Fiscal Year 2009, Waste Tank 29. Post chemical cleaning UT measurements were made in Tank 6 and the results are documented in SRNL-STI-2009-00560, Tank Inspection NDE Results Tank 6, Including Summary of Waste Removal Support Activities in Tanks 5 and 6. A total of 6669 photographs were made and 1276 visual and video inspections were performed during 2009. Twenty-Two new leaksites were identified in 2009. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.4. Fifteen leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. Five leaksites at Tank 6 were documented during tank wall/annulus cleaning activities. Two new leaksites were identified at Tank 19 during waste removal activities. Previously documented leaksites were reactivated at Tanks 5 and 12 during waste removal activities. Also, a very small amount of additional leakage from a previously identified leaksite at Tank 14 was observed.

  8. How Agencies Inspect. A Comparative Study of Inspection Policies in Eight Swedish Government Agencies

    International Nuclear Information System (INIS)

    Eight Swedish authorities with inspection tasks in the areas of health, safety, and environmental protection have been compared, namely the authorities responsible for nuclear safety, radiation protection, railway, marine and aviation safety, environmental protection, chemicals control, and health and safety on workplaces. Significant differences in inspection policies and practices between the authorities were found, such as: diverging definitions of supervision and inspection that complicate comparisons, different priority-setting principles for inspections, variations in inspection frequencies (between 13 and 0.03 inspections per company and year), different practices with respect to notifying companies before inspection visits, and in particular, large differences in the extent to which non-compliance with regulations is reported to legal authorities. It was concluded that these agencies have much to gain from increasing their cooperation in methods development, evaluation studies, and education of inspectors

  9. Regulatory inspection of the egyptian gamma irradiator using a proposed inspection checklist

    International Nuclear Information System (INIS)

    Regulatory inspections are one of the most important elements of a regulatory programme. It shall be performed in all areas of the regulatory responsibility and during all phases of siting, design, construction, commissioning, operation, maintenance and decommissioning of an irradiator facility. The egyptian mega gamma irradiator operating since december 1979 has a Co-60 source of about 400 kilo curies and is used mainly for sterilization of medical supplies and pharmaceuticals and for preservation of some food stuffs. The constructor (Nordion international Inc.) recommended an extensive inspection programme. In accordance with the international and national (2.3) regulations as well as the licensing conditions, the competent authority (NCNSRC) shall perform regulatory inspections both announced and unannounced. In order to facilitate the inspection task and to harmonize the inspection reports a checklist for inspection is proposed which can be used also as an inspection report form

  10. Remote automated ultrasonic inspection: New approaches to reduce radiation exposure and shorten inspection time

    International Nuclear Information System (INIS)

    Since 1977 General Electric (GE) has pioneered the use of trackless, remote inservice inspection (ISI) for boiling water reactor (BWR) vessels. Eleven baseline inspections and two inservice inspections have been performed using four different inspection systems. Since the first GE remote ISI system was placed into service in 1977, many advances in the technology have been made and development work is continuing. This paper describes some of those advances, and the development work currently in progress. The basic operating principles of the GE remote ISI system remain unchanged from the original concepts: a trackless vehicle featuring magnetic wheels is used for reactor pressure vessel (RPV) weld inspection, and removable tracks are used for nozzle inspection. Location on the RPV surface is accomplished by acoustic emission (AE) principles, ie., acoustic triangulation while vehicle positioning control, scanning and mapping of indications are done by a precision digital encoder guidance system. All of the above systems and the inspection itself, are controlled by a minicomputer

  11. A bivariate process model for maintenance and inspection planning

    International Nuclear Information System (INIS)

    The paper describes decision making about monitoring and maintenance of systems described by a general stochastic process. The system is monitored and preventive and corrective maintenance actions are carried out in response to the observed system state. The decision process is simplified by using an associated process as well as the underlying state as decision variables. The bivariate approach allows a wide class of models to be considered including long term memory within a simple probability structure. Both average cost and life-cycle cost models are used as the basis for decision making. The models generalize age replacement and other simple maintenance strategies. The approach can deal with failures that prevent the system functioning further, failures defined by regulation, or by economic considerations. The unified framework developed allows the inclusion of covariates and imperfect inspection or repair

  12. Results of automatic system implementation for Cofrentes nuclear power plant LPRM inspection execution

    International Nuclear Information System (INIS)

    During this presentation we are going to introduce the results of Cofrentes nuclear power plant automation of the detection system LPRM (Local Power Range Monitor) inspection procedure. An LPRM test system has been developed and it consists in a software application and data acquisition hardware that performs automatically the complete detection system process: 1) Refuelling, storage and operation inspection: ramp voltage generation, measured voltage plateaux evaluation, qualification report emission. 2) Historical analysis to scan burn evolution. The inspections differentiations are developed by the different specifications that it has to fulfil: 1) Operation inspection: it is made to check the fission bolt wearing, the detection system functioning and to analyse malfunctioning. From technical specifications and curves analyses it can be determined each LPRM substitution. 2) Storage inspection: it is made to check the correct functioning and isolation losses before being installed in the core during refueling. 3) Refueling inspection: it is checked that storage LPRM installation is correct and that they are ready for new fuel cycle. The software application LPRM test has been developed by National Instruments LabVIEWTM, and it performs the following actions: 1) Protocol IEEE-488 (GPI B) control of the source Keithley 237. This source generates the ramp voltage and measure voltage. 2) Information acquisition of storage, process and source, identifying LPRM and realization conditions of the same. 3) Data analysis and conditions report. 4) Historical comparative analysis. (Author)

  13. Potential of Uav-Based Laser Scanner and Multispectral Camera Data in Building Inspection

    Science.gov (United States)

    Mader, D.; Blaskow, R.; Westfeld, P.; Weller, C.

    2016-06-01

    Conventional building inspection of bridges, dams or large constructions in general is rather time consuming and often cost expensive due to traffic closures and the need of special heavy vehicles such as under-bridge inspection units or other large lifting platforms. In consideration that, an unmanned aerial vehicle (UAV) will be more reliable and efficient as well as less expensive and simpler to operate. The utilisation of UAVs as an assisting tool in building inspections is obviously. Furthermore, light-weight special sensors such as infrared and thermal cameras as well as laser scanner are available and predestined for usage on unmanned aircraft systems. Such a flexible low-cost system is realized in the ADFEX project with the goal of time-efficient object exploration, monitoring and damage detection. For this purpose, a fleet of UAVs, equipped with several sensors for navigation, obstacle avoidance and 3D object-data acquisition, has been developed and constructed. This contribution deals with the potential of UAV-based data in building inspection. Therefore, an overview of the ADFEX project, sensor specifications and requirements of building inspections in general are given. On the basis of results achieved in practical studies, the applicability and potential of the UAV system in building inspection will be presented and discussed.

  14. Results of automatic system implementation for Cofrentes nuclear power plant LPRM inspection execution

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-10-15

    During this presentation we are going to introduce the results of Cofrentes nuclear power plant automation of the detection system LPRM (Local Power Range Monitor) inspection procedure. An LPRM test system has been developed and it consists in a software application and data acquisition hardware that performs automatically the complete detection system process: 1) Refuelling, storage and operation inspection: ramp voltage generation, measured voltage plateaux evaluation, qualification report emission. 2) Historical analysis to scan burn evolution. The inspections differentiations are developed by the different specifications that it has to fulfil: 1) Operation inspection: it is made to check the fission bolt wearing, the detection system functioning and to analyse malfunctioning. From technical specifications and curves analyses it can be determined each LPRM substitution. 2) Storage inspection: it is made to check the correct functioning and isolation losses before being installed in the core during refueling. 3) Refueling inspection: it is checked that storage LPRM installation is correct and that they are ready for new fuel cycle. The software application LPRM test has been developed by National Instruments LabVIEWTM, and it performs the following actions: 1) Protocol IEEE-488 (GPI B) control of the source Keithley 237. This source generates the ramp voltage and measure voltage. 2) Information acquisition of storage, process and source, identifying LPRM and realization conditions of the same. 3) Data analysis and conditions report. 4) Historical comparative analysis. (Author)

  15. 40 CFR 62.14442 - What must my inspection include?

    Science.gov (United States)

    2010-07-01

    ...) Inspect HMIWI door and door gaskets for proper sealing; (f) Inspect motors for proper operation; (g... applicable; (k) Visually inspect waste bed (grates), and repair/ seal, as necessary; (l) For the burn...

  16. Post-Closure Inspection Report for the Tonopah Test Range, Nevada, for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Silvas, A. J.

    2014-03-03

    This report provides the results of the annual post-closure inspections conducted at the closed Corrective Action Units (CAUs) located on the Tonopah Test Range (TTR), Nevada. This report covers calendar year 2013 and includes inspection and repair activities completed at the following CAUs: • CAU 400: Bomblet Pit and Five Points Landfill (TTR) • CAU 407: Roller Coaster RadSafe Area (TTR) • CAU 424: Area 3 Landfill Complexes (TTR) • CAU 453: Area 9 UXO Landfill (TTR) • CAU 487: Thunderwell Site (TTR) Inspections were conducted according to the post-closure plans in the approved Closure Reports and subsequent correspondence with the Nevada Division of Environmental Protection. The post-closure inspection plans and subsequent correspondence modifying the requirements for each CAU are included in Appendix B. The inspection checklists are included in Appendix C. Field notes are included in Appendix D. Photographs taken during inspections are included in Appendix E. The annual post-closure inspections were conducted on May 14, 2013. Maintenance was performed at CAU 400, CAU 424, and CAU 453. At CAU 400, animal burrows were backfilled. At CAU 424, erosion repairs were completed at Landfill Cell A3-3, subsidence was repaired at Landfill Cell A3-4, and additional lava rock was placed in high-traffic areas to mark the locations of the surface grade monuments at Landfill Cell A3-3 and Landfill Cell A3-8. At CAU 453, two areas of subsidence were repaired and animal burrows were backfilled. Vegetation monitoring was performed at the CAU 400 Five Points Landfill and CAU 407 in June 2013. The vegetation monitoring report is included in Appendix F.

  17. Remote and unattended monitoring techniques

    International Nuclear Information System (INIS)

    In the last years, there has been a tremendous growth in the number of unattended assay and monitoring systems in the field. These systems have enabled reduced presence of inspectors while increasing the verification coverage. As part of the Strengthened safeguards System and in particular as part of the measures to improve the cost-effectiveness of safeguards, the possibility of remote transfer of authenticated and encrypted video surveillance, seals and radiation sensor data via telephone or special satellite links have been demonstrated and the necessary arrangements and infrastructure have been prepared. The evaluation of field trials of the remote monitoring systems have shown that the systems are effective in monitoring events of safeguards relevance in near real times. The systems are competitive from a cost standpoint when compared to current methods. The reduction of inspection efforts can be realized by application of remote monitoring technique with scheduled inspections and more effectively with the short notice or unannounced random inspections. It is expected that, upon completion of the necessary arrangements with the Member States authorities, the safeguards department will implement the technique widely before the year 2000

  18. Scientific Opinion on the public health hazards to be covered by inspection of meat (bovine animals

    Directory of Open Access Journals (Sweden)

    EFSA Panel on Biological Hazards (BIOHAZ

    2013-06-01

    Full Text Available A risk ranking process identified Salmonella spp. and pathogenic verocytotoxin-producing Escherichia coli (VTEC as current high-priority biological hazards for meat inspection of bovine animals. As these hazards are not detected by traditional meat inspection, a meat safety assurance system for the farm-to-chilled carcass continuum using a risk-based approach was proposed. Key elements of the system are risk-categorisation of slaughter animals for high-priority biological hazards based on improved food chain information, as well as risk-categorisation of slaughterhouses according to their capability to control those hazards. Omission of palpation and incision during post-mortem inspection for animals subjected to routine slaughter may decrease spreading and cross-contamination with the high-priority biological hazards. For chemical hazards, dioxins and dioxin-like polychlorinated biphenyls were ranked as being of high potential concern; all other substances were ranked as of medium or lower concern. Monitoring programmes for chemical hazards should be more flexible and based on the risk of occurrence, taking into account the completeness and quality of the food chain information supplied and the ranking of chemical substances, which should be regularly updated to include new hazards. Control programmes across the food chain, national residue control programmes, feed control and monitoring of environmental contaminants should be better integrated. Meat inspection is a valuable tool for surveillance and monitoring of animal health and welfare conditions. Omission of palpation and incision would reduce detection effectiveness for bovine tuberculosis and would have a negative impact on the overall surveillance system especially in officially tuberculosis free countries. The detection effectiveness for bovine cysticercosis, already low with the current meat inspection system, would result in a further decrease, if palpation and incision are removed

  19. A design condition for incorporating human judgement into monitoring systems

    International Nuclear Information System (INIS)

    In safety monitoring, there exists an uncertainty situation in which the sensor cannot detect whether or not the monitored object is in danger. For the uncertainty zone identified by a non-homogeneous safety monitoring system that utilizes two types of sensors with different thresholds, operators or experts are expected to judge whether the real state is safe or dangerous on the basis of additional information from a detailed inspection or other related sensors output. However, the activities for inspection performed by relevant humans may require additional cost and introduce inspection errors. The present article proposes two types of an automatic monitoring system not involving any human inspection or a human-machine (H-M) cooperative monitoring system with inspection. In order to compare the systems, an approach based on the Dempster-Shafer theory is proposed as uncertainty analysis by this theory (it is simpler than by the traditional Bayesian approach). By comparing their expected losses as a result of failed dangerous failures or failed safe failures as well as the inspection errors, the condition is determined under which H-M cooperative systems incorporating human judgements are more effective than automatic monitoring systems

  20. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2007-01-01

    A basic assumption often made in risk/reliability based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no-...... is llustrated forwelded steel details in platforms. Systems effects are considered including use of dependence between inspection and failure events in different components for inspection planning.......A basic assumption often made in risk/reliability based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no...... time intervals for ageing structures. Different approaches for updating inspection plans for older installations are proposed.The most promising method consists in increasing the rate of crack initiations at the end of the expected lifetime - corresponding to a bath-tube hazard rate effect.The approach...

  1. Heat exchanger tube inspection using ultrasonic arrays

    International Nuclear Information System (INIS)

    Tubing used in industrial heat exchangers is often subject to failure caused by corrosion and cracking. Technical conferences are used as a forum in the steam generator industry to ensure that the failure mechanisms are well understood and that the quality of the heat exchanger is maintained. The quality of a heat exchanger can be thought of as its ability to operate to design specifications over its intended life. This is the motivation to inspect and evaluate these devices periodically. Inspection, however, normally requires shutdown of the heat exchanger which is costly but is much more acceptable than an unscheduled shutdown due to failure of a tube. Therefore, the degree of inspection is established by balancing the cost of inspection with the risk of a tube failure. Any method of reducing the cost of inspection will permit a higher degree of inspection and, therefore, improve heat exchanger quality. This paper reviews the design and performance of an improved method of ultrasonic inspection of heat exchanger tubing with emphasis on applications in the nuclear industry

  2. Inspection of licensee activities in emergency planning

    International Nuclear Information System (INIS)

    The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries Following discussions at several meetings on the topic of what is expected by the regulatory body regarding inspection criteria, WGIP proposed putting together a compilation of Member countries practices on regulatory inspection practices with respect to licensee emergency planning. CNRA approved this task and this report. Information was collected from a questionnaire which was issued in 1996. The report presents information on regulatory inspection activities with respect to emergency planning in NEA Member countries. The focus of the report is on the third section. It reviews the similarities and differences in inspection practices to evaluate compliance with the requirements over which the regulatory body (RB) has jurisdiction

  3. Poolside inspection facility for PWR fuel assemblies

    International Nuclear Information System (INIS)

    Pool side inspection programme for LWRs started in India with the inspection of BWR fuel assemblies at Tarapur and this involved sipping, visual inspection, UT and Eddy current testing. In view of the possibility of having WWER type of reactors in our country, a R and D program has been initiated for study of behavior of these types of fuel. The program would involve irradiation, pool side inspection and hot cell examination of specially designed fuel assemblies. Well characterized fuel assemblies irradiated in research reactor are transferred to the fuel pool with the help of fuel transfer system. The fuel assemblies are taken out of the transfer system, sipping test performed and de channeled using under water handling and cutting tools. The fuel pins are then taken out of assembly and loaded on to the stand for underwater UT and Eddy current testing. The details of the handling and inspection facilities provided in pool for inspection of the hexagonal fuel assemblies has been discussed in the text. Dismantling and inspection procedure used for control assembly pins have also been discussed. (author)

  4. UF{sub 6} cylinder inspections at PGDP

    Energy Technology Data Exchange (ETDEWEB)

    Lamb, G.W.; Whinnery, W.N. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

    1991-12-31

    Routine inspections of all UF{sub 6} cylinders at the Paducah Gaseous Diffusion Plant have been mandated by the Department of Energy. A specific UF{sub 6} cylinder inspection procedure for what items to inspect and training for the operators prior to inspection duty are described. The layout of the cylinder yards and the forms used in the inspections are shown. The large number of cylinders (>30,000) to inspect and the schedule for completion on the mandated time table are discussed. Results of the inspections and the actions to correct the deficiencies are explained. Future inspections and movement of cylinders for relocation of certain cylinder yards are defined.

  5. Advanced maintenance, inspection & repair technology for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hinton, B.M.

    1994-12-31

    Maintenance, inspection, and repair technology for nuclear power plants is outlined. The following topics are discussed: technology for reactor systems, reactor refueling bridge, fuel inspection system, fuel shuffling software, fuel reconstitution, CEA/RCCA/CRA inspection, vessel inspection capabilities, CRDM inspection and repair, reactor internals inspection and repair, stud tensioning system, stud/nut cleaning system, EDM machining technology, MI Cable systems, core exit T/C nozzle assemblies, technology for steam generators, genesis manipulator systems, ECT, UT penetrant inspections, steam generator repair and cleaning systems, technology for balance of plant, heat exchangers, piping and weld inspections, and turbogenerators.

  6. Maintenance Planning of Offshore Wind Turbine using Condition Monitoring Information

    DEFF Research Database (Denmark)

    Ramírez, José G. Rangel; Sørensen, John Dalsgaard

    2009-01-01

    Deterioration processes such as fatigue and corrosion are typically affecting offshore structures. To "control" this deterioration, inspection and maintenance activities are developed. Probabilistic methodologies represent an important tool to identify the suitable strategy to inspect and control...... the deterioration in structures such as offshore wind turbines (OWT). Besides these methods, the integration of condition monitoring information (CMI) can optimize the mitigation activities as an updating tool. In this paper, a framework for risk-based inspection and maintenance planning (RBI) is...... modes t integrate CMI in the RBI approach for optimal planning of inspection and maintenance. As part of the results, the life cycle reliabilities and inspection times are calculated, showing that earlier inspections are needed at in-wind farm sites. This is expected due to the wake turbulence...

  7. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2011-06-23

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

  8. Recent Advances in Structural Health Monitoring

    International Nuclear Information System (INIS)

    Emerging sensor-based structural health monitoring (SHM) technology can play an important role in inspecting and securing the safety of aging civil infrastructure, a worldwide problem. However, implementation of SHM in civil infrastructure faces a significant challenge due to the lack of suitable sensors and reliable methods for interpreting sensor data. This paper reviews recent efforts and advances made in addressing this challenge, with example sensor hardware and software developed in the author's research center. It is proposed to integrate real-time continuous monitoring using on structure sensors for global structural integrity evaluation with targeted NDE inspection for local damage assessment

  9. Increasing Inspectability of Hardware and Software for Arms Control and Nonproliferation Regimes

    Energy Technology Data Exchange (ETDEWEB)

    White, G

    2001-07-18

    As the U.S. and the Russian Federation get closer to deploying systems for monitoring nuclear material within arms control and nonproliferation transparency regimes, the level of inspectability of the system hardware and software must increase beyond the systems demonstrated to date. These systems include the Trilateral Initiative prototype, the Fissile Material Transparency Technology Demonstration (FMTTD) system, and the Trusted Radiation Attribute Demonstration System (TRADS). Toward this goal, several alternative technologies will be discussed along with ways in which they would increase inspectability. Some examples of such technologies include the use of microcontrollers instead of fully capable computers, open source operating systems, rantime environments, and compilers.

  10. Remote systems for inspection and repair of a highly active dissolver

    International Nuclear Information System (INIS)

    An integrated remote handling system has been built to carry out inspections inside a nuclear fuel dissolver vessel. Tooling is provided to effect repairs to the dissolver if required. The system incorporates a novel manipulator, closed circuit television (CCTV), endoscopes, ultrasonic inspection probes, remote machining and remote tungsten inert gas (TIG) welding packages. An advanced computer control system is provided to allow the operator to monitor, interlock and control the complex equipment. Technique research is complete and non-active test results to date are reported. (Author)

  11. The role of the United States Food Safety and Inspection Service after the Chernobyl accident

    International Nuclear Information System (INIS)

    The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry

  12. The proposed detailed optical inspection of CAGR fuel elements in power station cooling

    International Nuclear Information System (INIS)

    Equipment is under development for optical inspection of CAGR fuel elements under water in power station cooling ponds. Such inspection is regarded as an effective adjunct to normal in-cave PIE and is supported by various experimental trials, the main results of which are described. The system is based on a special borescope coupled to a t.v. camera and it is anticipated that surface condition can be monitored with a resolution of about 20 microns, to a depth of 250mm below the top brace. Furthermore, a limited amount of mensuration is planned. Consideration is also given to implementation of the equipment at a power station. (author)

  13. Inspection device for reactor inside

    International Nuclear Information System (INIS)

    A driving mechanism main body comprising a securing cylinder and a rotating cylinder connected with each other is suspended from a shielding plug of a reactor container. A rotating motor incorporating a position sensitive detector is disposed in the securing cylinder. A scanning motor each incorporating a position sensitive detector and an inclination controlling motor are disposed in the rotating cylinder, and one end of an arm driven by the scanning motor and the inclination controlling motor is attached to the rotating cylinder and the other end of the arm is attached to an ultrasonic wave transducer. Further, a permanent magnet of high curie temperature is used for a rotor of a motor for driving the ultrasonic wave transducer, and an inorganic heat resistant insulation material made of compounds of high melting point used for coating the windings of each of the motors and the position sensitive detectors. With such a constitution, highly accurate inspection can be conducted by a small-sized device of high moving performance. Further, electrical, mechanical and radioactive degradations can be prevented under a liquid metal temperature, to ensure the integrity for a long period of time. (N.H.)

  14. Autonomous Robotic Inspection in Tunnels

    Science.gov (United States)

    Protopapadakis, E.; Stentoumis, C.; Doulamis, N.; Doulamis, A.; Loupos, K.; Makantasis, K.; Kopsiaftis, G.; Amditis, A.

    2016-06-01

    In this paper, an automatic robotic inspector for tunnel assessment is presented. The proposed platform is able to autonomously navigate within the civil infrastructures, grab stereo images and process/analyse them, in order to identify defect types. At first, there is the crack detection via deep learning approaches. Then, a detailed 3D model of the cracked area is created, utilizing photogrammetric methods. Finally, a laser profiling of the tunnel's lining, for a narrow region close to detected crack is performed; allowing for the deduction of potential deformations. The robotic platform consists of an autonomous mobile vehicle; a crane arm, guided by the computer vision-based crack detector, carrying ultrasound sensors, the stereo cameras and the laser scanner. Visual inspection is based on convolutional neural networks, which support the creation of high-level discriminative features for complex non-linear pattern classification. Then, real-time 3D information is accurately calculated and the crack position and orientation is passed to the robotic platform. The entire system has been evaluated in railway and road tunnels, i.e. in Egnatia Highway and London underground infrastructure.

  15. Risk Based Inspection Planning of Ageing Structures

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, Gerhard

    2008-01-01

    system aspects are considered incl. assessment of the acceptable annual probability of failure for one component dependent on the number of critical components. Information obtained from inspection of one component can be used not only to update the inspection plan for that component, but also for other...... nearby components. An example indicates that a high degree of correlation between the uncertain parameters in different components is needed in order to obtain substantial information which can be used in inspection planning. Fatigue failure of one (or more) components does not necessary imply total...

  16. Eddy current inspection of graphite fiber components

    Science.gov (United States)

    Workman, G. L.; Bryson, C. C.

    1990-01-01

    The recognition of defects in materials properties still presents a number of problems for nondestructive testing in aerospace systems. This project attempts to utilize current capabilities in eddy current instrumentation, artificial intelligence, and robotics in order to provide insight into defining geometrical aspects of flaws in composite materials which are capable of being evaluated using eddy current inspection techniques. The unique capabilities of E-probes and horseshoe probes for inspecting probes for inspecting graphite fiber materials were evaluated and appear to hold great promise once the technology development matures. The initial results are described of modeling eddy current interactions with certain flaws in graphite fiber samples.

  17. MRT fuel element inspection at Dounreay

    International Nuclear Information System (INIS)

    To ensure that their production and inspection processes are performed in an acceptable manner, ie. auditable and traceable, the MTR Fuel Element Fabrication Plant at Dounreay operates to a documented quality system. This quality system, together with the fuel element manufacturing and inspection operations, has been independently certified to ISO9002-1987, EN29002-1987 and BS5750:Pt2:1987 by Lloyd's Register Quality Assurance Limited (LRQA). This certification also provides dual accreditation to the relevant German, Dutch and Australian certification bodies. This paper briefly describes the quality system, together with the various inspection stages involved in the manufacture of MTR fuel elements at Dounreay

  18. Hanford site post NPH building inspection plan

    Energy Technology Data Exchange (ETDEWEB)

    Wagenblast, G.R., Westinghouse Hanford

    1996-09-12

    This plan establishes consistent post-NPH building inspection procedures and defines a procedure for prioritization of buildings for inspection to ensure the safety of facilities prior to reentry. Qualification of systems for restart of operation is not included. This plan takes advantage, where possible, of existing national procedures for post-NPH inspection of buildings, of existing structural design and evaluation documentation of Hanford facilities, and current and proposed seismic instrumentation located throughout the Hanford site. A list of buildings, prioritized according to current building safety function and building vulnerability (without regard for or information about a damaging natural forces event) is provided.

  19. A quantum extension to inspection game

    Science.gov (United States)

    Deng, Xinyang; Deng, Yong; Liu, Qi; Chang, Shuhua; Wang, Zhen

    2016-07-01

    Quantum game theory is a new interdisciplinary field between game theory and system engineering research. In this paper, we extend the classical inspection game into a quantum game version by quantizing the strategy space and importing entanglement between players. Our results show that the quantum inspection game has various Nash equilibria depending on the initial quantum state of the game. It is also shown that quantization can respectively help each player to increase his own payoff, yet fails to bring Pareto improvement for the collective payoff in the quantum inspection game.

  20. MRT fuel element inspection at Dounreay

    Energy Technology Data Exchange (ETDEWEB)

    Gibson, J.

    1997-08-01

    To ensure that their production and inspection processes are performed in an acceptable manner, ie. auditable and traceable, the MTR Fuel Element Fabrication Plant at Dounreay operates to a documented quality system. This quality system, together with the fuel element manufacturing and inspection operations, has been independently certified to ISO9002-1987, EN29002-1987 and BS5750:Pt2:1987 by Lloyd`s Register Quality Assurance Limited (LRQA). This certification also provides dual accreditation to the relevant German, Dutch and Australian certification bodies. This paper briefly describes the quality system, together with the various inspection stages involved in the manufacture of MTR fuel elements at Dounreay.

  1. Optical technologies for measurement and inspection

    International Nuclear Information System (INIS)

    Ontario Hydro has benefited from specialized optical measurement techniques such as FRILS (fret replica inspection laser system), which permits in-house inspections of pressure tube replicas and has been estimated to save $2M per year. This paper presents a brief overview of (1) FRILS, (2) OPIT (in-reactor Optical Profilometry Inspection Tool), (3) miniature optical probe for steam generator tubes, (4) laser vibrometer used for end-fitting vibration, and (5) computer vision to recognize the ends of fuel bundles and automatically measure their lengths. (author)

  2. Risk-based methodology for USNRC inspections

    International Nuclear Information System (INIS)

    This paper describes the development and trial applications of a risk-based methodology to enhance the inspection processes for US nuclear power plants. Objectives of risk-based methods to complement prescriptive engineering approaches in US Nuclear Regulatory Commission (USNRC) inspection programs are presented. Insights from time-dependent risk profiles of plant configurational from Individual Plant Evaluation (IPE) studies were integrated to develop a framework for optimizing inspection efforts in NRC regulatory initiatives. Lessons learned from NRC pilot applications of the risk-based methodology for evaluation of the effectiveness of operational risk management programs at US nuclear power plant sites are also discussed

  3. Storage monitoring systems for the year 2000

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, C.; Pollock, R.

    1997-12-31

    In September 1993, President Clinton stated the US would ensure that its fissile material meet the highest standards of safety, security, and international accountability. Frequent human inspection of the material could be used to ensure these standards. However, it may be more effective and less expensive to replace these manual inspections with virtual inspections via remote monitoring technologies. To prepare for this future, Sandia National Laboratories has developed several monitoring systems, including the Modular Integrated Monitoring System (MIMS) and Project Straight-Line. The purpose of this paper is to describe a Sandia effort that merges remote monitoring technologies into a comprehensive storage monitoring system that will meet the near-term as well as the long-term requirements for these types of systems. Topics discussed include: motivations for storage monitoring systems to include remote monitoring; an overview of the needs and challenges of providing a storage monitoring system for the year 2000; an overview of how the MIMS and Straight-Line can be enhanced so that together they create an integrated and synergistic information system by the end of 1997; and suggested milestones for 1998 and 1999 to assure steady progress in preparing for the needs of 2000.

  4. Storage monitoring systems for the year 2000

    International Nuclear Information System (INIS)

    In September 1993, President Clinton stated the US would ensure that its fissile material meet the highest standards of safety, security, and international accountability. Frequent human inspection of the material could be used to ensure these standards. However, it may be more effective and less expensive to replace these manual inspections with virtual inspections via remote monitoring technologies. To prepare for this future, Sandia National Laboratories has developed several monitoring systems, including the Modular Integrated Monitoring System (MIMS) and Project Straight-Line. The purpose of this paper is to describe a Sandia effort that merges remote monitoring technologies into a comprehensive storage monitoring system that will meet the near-term as well as the long-term requirements for these types of systems. Topics discussed include: motivations for storage monitoring systems to include remote monitoring; an overview of the needs and challenges of providing a storage monitoring system for the year 2000; an overview of how the MIMS and Straight-Line can be enhanced so that together they create an integrated and synergistic information system by the end of 1997; and suggested milestones for 1998 and 1999 to assure steady progress in preparing for the needs of 2000

  5. An intelligent fetal monitoring system

    International Nuclear Information System (INIS)

    An intelligent monitoring system is constructed by a multi-micro-computer system. The monitoring signals are fetal heart rate (FHR) and uterine contraction (UC) through the conventional monitoring device for a day until the delivery. These signals are fed to a micro-computer in digital format, and evaluated by the computer in real time according to the diagnostic algorithm of the expert physician. Monitoring signals are always displayed on the CRT screen and in the case of dangerous state of the fetus, warning signal will appear on the screen and the doctor or nurse will be called. All these signals are sent to the next micro-computer with 10MB hard disk system. On this computer, the doctor and nurse can retrieve and inspect the details of the process by clock-key and/or events-key. After finishing monitoring process, summarized report is constructed and printed out on the paper

  6. Process Specification for Eddy Current Inspection

    Science.gov (United States)

    Koshti, Ajay

    2011-01-01

    This process specification establishes the minimum requirements for eddy current inspection of flat surfaces, fastener holes, threaded fasteners and seamless and welded tubular products made from nonmagnetic alloys such as aluminum and stainless steel.

  7. Emerging nondestructive inspection methods for aging aircraft

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, A; Dahlke, L; Gieske, J [and others

    1994-01-01

    This report identifies and describes emerging nondestructive inspection (NDI) methods that can potentially be used to inspect commercial transport and commuter aircraft for structural damage. The nine categories of emerging NDI techniques are: acoustic emission, x-ray computed tomography, backscatter radiation, reverse geometry x-ray, advanced electromagnetics, including magnetooptic imaging and advanced eddy current techniques, coherent optics, advanced ultrasonics, advanced visual, and infrared thermography. The physical principles, generalized performance characteristics, and typical applications associated with each method are described. In addition, aircraft inspection applications are discussed along with the associated technical considerations. Finally, the status of each technique is presented, with a discussion on when it may be available for use in actual aircraft maintenance programs. It should be noted that this is a companion document to DOT/FAA/CT-91/5, Current Nondestructive Inspection Methods for Aging Aircraft.

  8. Typical NRC inspection procedures for model plant

    International Nuclear Information System (INIS)

    A summary of NRC inspection procedures for a model LEU fuel fabrication plant is presented. Procedures and methods for combining inventory data, seals, measurement techniques, and statistical analysis are emphasized

  9. Regular inspection of safety and relief valves

    International Nuclear Information System (INIS)

    Safety valve concepts with self control mechanisms are in regular use in nuclear power plants in the Federal Republic of Germany. The effect of defects in these valves and the influence on inspection practices is discussed. 12 figs., 1 tab

  10. Food Service Establishment Inspections: Beginning 2005 (ACTIVE)

    Data.gov (United States)

    U.S. Department of Health & Human Services — This data includes the name and location of active food service establishments and the violations that were found at the time of the inspection. Active food service...

  11. Real-Time Inspection Of Currency

    Science.gov (United States)

    Blazek, Henry

    1986-12-01

    An automatic inspection machine, designed and manufactured by the Perkin-Elmer Corporation for the U.S. Bureau of Engraving and Printing, is capable of real-time inspection of currency at rates compatible with the output of modern high-speed printing presses. Inspection is accomplished by comparing test notes (in 32-per-sheet format) with reference notes stored in the memory of a digital computer. This paper describes the development of algorithms for detecting defective notes, one of the key problems solved during the development of the inspection system. Results achieved on an analytical model, used for predicting probability of false alarms and probability of detecting typically defective notes, are compared to those obtained by system simulation.

  12. Optimal inspection Strategies for Offshore Structural Systems

    DEFF Research Database (Denmark)

    Faber, M. H.; Sørensen, John Dalsgaard; Kroon, I. B.

    to perform optimal inspection and repair strategies for structural components subject to uncertain loading conditions and material behavior. In this paper this methodology is extended to inelude also system failure i.e. failure of a given sub set of all the structural components. This extension...... ineludes a mathematical framework for the estimation of the failure and repair costs a.ssociated with systems failure. Further a strategy for selecting the components to inspect based on decision tree analysis is suggested. Methods and analysis schemes are illustrated by a simple example.......Optimal planning of inspection and maintenance strategies for structures has become a subject of increasing interest especially for offshore structures for which large costs are associated with structural failure, inspections and repairs. During the last five years a methodology has been formulated...

  13. On automatic visual inspection of reflective surfaces

    DEFF Research Database (Denmark)

    Kulmann, Lionel

    1995-01-01

    surveyed visual inspection system design methods and presented available image processing hardware to perform high resolution image capture. We present general usable practical visual inspection system solutions, when performing high resolution visual inspection of surfaces. We have presented known and new...... surfaces, providing new and exciting applications subject to automated visual inspection. Several contextual features have been surveyed along with introduction of novel methods to perform data-dependent enhancement of local surface appearance . Morphological methods have been described and utilized in...... algorithms for detecting 3-dimensional surface damages based on images from a novel structured lighting setup enhancing the appearance of these defects in specular surfaces. A hardware implementable polynomial classifier structure has been described and compared to better known techniques based on...

  14. Cronos, an advanced system for RCCA inspection

    International Nuclear Information System (INIS)

    The Rod Cluster Control Assembly (RCCA) is critical for the safe operation of nuclear power plants since its main function is to control neutron activity inside the core. These assemblies have a spider-shaped structure and are made up of a set of rods filled with a neutron absorbent. They are usually partially inserted in the fuel assemblies (normally only the lower part during normal operation) and may be completely inserted when necessary. The degradation mechanisms that may typically occur during the operation of the rod cluster control assemblies are as follows: - wear caused by friction of the rods against their guide structures; - increase in the diameter of the tips of the rods caused by irradiation-induced swelling of the absorbent. This increase in diameter causes deformation of the rod, which may generate cracks in the material of the rod and eventually hinder its insertion in the fuel assemblies. The RCCA's have traditionally been inspected with a view to verifying their correct status and guaranteeing their operability. Since the 1990's, Tecnatom has been performing eddy current inspections using systems based on different techniques (wrap-around, pancake and rotary probes). The new CRONOS inspection system (IS) developed by Tecnatom combines the eddy current (ET) and ultrasonic (UT) methods, incorporating the capacity to detect and characterise all the possible degradations that affect the RCCA's. At present Tecnatom has a mechanical system applicable to RCCA's for 17x17 fuel assemblies and is developing a second unit for 16x16 assemblies. Development of the CRONOS IS began in 2011 and the system has been used successfully in three inspections at Spanish NPPs (2 at Vandellos 2 and 1 at Asco 1) and one inspection in China (Ling Ao 2 NPP). The control cluster rods inspected are made of AISI304 or 316 stainless steel, with a chrome or nitride surface treatment, and have a nominal outer diameter of 9.68 mm and a thickness of between 0

  15. Ultrasonic inspection system for powder metallurgy parts

    OpenAIRE

    Turó Peroy, Antonio; Chávez Domínguez, Juan Antonio; García Hernández, Miguel J.; Bulkai, András; Tomek, Péter; Tóth, Gabor; Gironés, Ana; Salazar Soler, Jorge

    2013-01-01

    The demand for powder metallurgy (P/M) parts in its traditional automotive market is predicted to grow, but future sector expansion depends directly upon its capability to manufacture zero-defect parts for industries such as aerospace and medicine. The lack of adequate inspection systems has important implications from the point of view of quality assurance, since it increases the costs, time and wasted material. In recent years the applicability of several techniques for the inspection of P/...

  16. Development Of NRU Reflector Wall Inspection System

    OpenAIRE

    Simpson, N.; B.V. Luloff; N. Zahn; R. Lumsden

    2013-01-01

    In 2009 May, the National Research Universal (NRU) calandria leaked. During the next year, the calandria was inspected with six new Non-Destructive Evaluation (NDE) techniques to determine the extent of the corrosion, repaired, and finally the repair was inspected with four additional new NDE techniques before the reactor was returned to service.The calandria is surrounded by a light-water reflector vessel fabricated from the same material as the calandria vessel. Concerns that the same corro...

  17. Typical IAEA inspection procedures for model plant

    International Nuclear Information System (INIS)

    This session briefly refers to the legal basis for IAEA inspections and to their objectives. It describes in detail the planning and performance of IAEA inspections, including the examination of records, the comparison of facility records with State reports, flow and inventory verifications, the design of statistical sampling plans, and Agency's independent verification measurements. In addition, the session addresses the principles of Material Balance and MUF evaluation, as well as the content and format of summary statements and related problems

  18. A quantum extension to inspection game

    OpenAIRE

    Deng, Xinyang; Deng, Yong; Liu, Qi; Zhen WANG

    2015-01-01

    Quantum game theory is a new interdisciplinary field between game theory and physical research. In this paper, we extend the classical inspection game into a quantum game version by quantizing the strategy space and importing entanglement between players. Our result shows that the quantum inspection game has various Nash equilibrium depending on the initial quantum state of the game. It is also shown that quantization can respectively help each player to increase his own payoff, yet fails to ...

  19. Optical techniques for nuclear reactor inspection

    International Nuclear Information System (INIS)

    Optical inspection techniques available and relevant to the various stages of the life cycle of a nuclear reactor are briefly reviewed. Experience in the three main types of nuclear reactor of interest to the CEGB, Magnox, AGR and PWR, is discussed. Conventional optical systems and stereoscopic viewing systems are described together with specialized and novel techniques, mainly Marchwood Engineering Laboratory's developments, which have proved valuable in tackling a variety of inspection problems. (U.K.)

  20. ACEC: remote inspection, remote intervention, autonomous vehicle

    International Nuclear Information System (INIS)

    Early in 1979, the accident at the TMI-2 nuclear power station focused attention on the lack of inspection and intervention means in containments where high radiation levels do not allow the entrance of humans. Recent years have seen a trend towards significant developments in the application of robotic technology to maintenance and inspection in nuclear facilities. This paper presents the general development concept and the technical specifications of a mobile robot

  1. Computer Aided Visual Inspection of Aircraft Surfaces

    OpenAIRE

    Rafia Mumtaz; Mustafa Mumtaz; Atif Bin Mansoor; Hassan Masood

    2012-01-01

    Non Destructive Inspections (NDI) plays a vital role in aircraft industry as it determines the structural integrity of aircraft surface and material characterization. The existing NDI methods are time consuming, we propose a new NDI approach using Digital Image Processing that has the potential to substantially decrease the inspection time. Automatic Marking of cracks have been achieved through application of Thresholding, Gabor Filter and Non Subsampled Contourlet transform. For a novel meth...

  2. Proposal of inspection methodology for environment radiological control; Proposta de metodologia de inspecao para controle radiologico ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Nadia Soido Falcao

    2005-07-01

    The Radiation Protection and Dosimetry Institute (IRD) of the Brazilian Nuclear Energy Commission (CNEN) is in charge of verifying that the self-monitoring operator is effective to control the radiological quality of environmental around the nuclear facilities and carried out in accordance with the regulatory requirements. While a long time, the verification of compliance was kept by the conduction of large scale monitoring programs around all the authorized installations. The IRD decided to reformulate its performance behavior, starting another kind of control program, due to the number increase of nuclear installations and the diversity of activities conducted by the operators. This program, so-called Monitoring Control Program (PCM) is a regulatory activity developed by the Environmental Impact Assessment Service (SEAIA) of IRD and has the aim of check the effectiveness of authorized self-control. Actually the regulatory control of environmental radiological integrity around the authorized nuclear installation essentially depends on the effectiveness of regulatory inspections fulfilled by the SEAIA/IRD. Due to the implementation of modern practices of management in the IRD, specially the quality management system on regulatory inspection activities, emerged the need of unify these actions. It was also necessary to establish standard procedures required for inspection conduction. This work proposes one methodology for the inspections of environmental radiological control suitable to assure the compliance and effectiveness of environmental and effluent monitoring programs conducted by the operator, through the systematic verification of compliance and data quality assessment. The proposed methodology seeks to attend the appeals for high control standards of environment protection and public health. Here, we presented as products of this work: The inspection handbook and checklists for inspections; one framework for sampling, handling, recording and reporting of

  3. Development of NRU reflector wall inspection system

    International Nuclear Information System (INIS)

    In 2009 May, the National Research Universal (NRU) calandria leaked. During the next year, the calandria was inspected with six new Non-Destructive Evaluation (NDE) techniques to determine the extent of the corrosion, repaired, and finally the repair was inspected with four additional new NDE techniques before the reactor was returned to service. The calandria is surrounded by a light-water reflector vessel fabricated from the same material as the calandria vessel. Concerns that the same corrosion mechanism had damaged the reflector vessel led to the development of a system to inspect the full circumference of the reflector wall for corrosion damage. The inspection region could only be accessed through 64 mm diameter ports, was 10 m below the port, and had to be inspected from the corroded surface. The ultrasonic technique was designed to produce a closely spaced wall thickness (WT) grid over an area of approximately 5 m2 on the corroded surface using a very small probe holder. This paper describes the Reflector Wall Inspection (RWI) development project and the system that resulted. (author)

  4. Development of NRU reflector wall inspection system

    Energy Technology Data Exchange (ETDEWEB)

    Lumsden, R.H.; Luloff, B.V.; Zahn, N.; Simpson, N., E-mail: lumsdenr@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2013-06-15

    In 2009 May, the National Research Universal (NRU) calandria leaked. During the next year, the calandria was inspected with six new Non-Destructive Evaluation (NDE) techniques to determine the extent of the corrosion, repaired, and finally the repair was inspected with four additional new NDE techniques before the reactor was returned to service. The calandria is surrounded by a light-water reflector vessel fabricated from the same material as the calandria vessel. Concerns that the same corrosion mechanism had damaged the reflector vessel led to the development of a system to inspect the full circumference of the reflector wall for corrosion damage. The inspection region could only be accessed through 64 mm diameter ports, was 10 m below the port, and had to be inspected from the corroded surface. The ultrasonic technique was designed to produce a closely spaced wall thickness (WT) grid over an area of approximately 5 m2 on the corroded surface using a very small probe holder. This paper describes the Reflector Wall Inspection (RWI) development project and the system that resulted. (author)

  5. SICOM: On-site inspection systems

    International Nuclear Information System (INIS)

    As the irradiation conditions become more demanding for the fuel than in the past, there is a need for surveillance programs to gather in-reactor operating experience. The data obtained in these programs can be used to assess the performance of current fuel designs and the improvements incorporated to the fuel assembly design, the performance of the advanced cladding alloys, etc. In these regards, valuable data is obtained from on-site fuel inspections. These on-site data comprise fuel assembly dimensional data such as length and distortion (tilt, twist and bow) and fuel rod data such as length and oxide thickness. These data have to be reliable and accurate to be useful thus, demanding a high precision inspection equipment. However, the inspection equipment has to be also robust and flexible enough to operate in the plant spent fuel pool and, sometimes, without interfering in the works carried out during a plant outage. To meet these requirements, during the past years ENUSA and TECNATOM have developed two on-site inspection systems. While the first system can perform most of the typical measurements in a stand-alone manner thus, without interfering with the critical path of the reload, the second one reduces the inspection time but requires using the plant capabilities. The paper describes both equipment for fuel on-site inspection, their characteristics and main features. (author)

  6. Conceptual design for transmission line inspection robot

    International Nuclear Information System (INIS)

    Power transmission line is used for power distribution purposes due to their cost effective measure compared to underlying cable. However, prolonged exposure to natural weather may cause fatigue stress to the lines as well as induce material failure. Therefore, periodical line inspection is considered uttermost important as a preventive measure to avoid power outage. However, transmission line inspection has always been a high risk and expensive work. Hazardous works that may harm operator as well as routine that requires precise handling can be performed by robots. Various types of robots have been designed and developed for line inspection but only perform well on a straight and continuous line. As these robots encounter an obstacle during the inspection, then the real problem in terms of robot stability and smooth operation arises. In this paper, conceptual design and evaluation for transmission line inspection robot is presented. The inspection robot mobile robot must be able to bypass or avoid obstacles as it travels along the power transmission line.

  7. Deposition uniformity inspection in IC wafer surface

    International Nuclear Information System (INIS)

    This paper focuses on the task of automatic visual inspection of color uniformity on the surface of integrated circuits (IC) wafers arising from the layering process. The oxide thickness uniformity within a given wafer with a desired target thickness is of great importance for modern semiconductor circuits with small oxide thickness. The non-uniform chemical vapor deposition (CVD) on a wafer surface will proceed to fail testing in Wafer Acceptance Test (WAT). Early detection of non-uniform deposition in a wafer surface can reduce material waste and improve production yields. The fastest and most low-priced inspection method is a machine vision-based inspection system. In this paper, the proposed visual inspection system is based on the color representations which were reflected from wafer surface. The regions of non-uniform deposition present different colors from the uniform background in a wafer surface. The proposed inspection technique first learns the color data via color space transformation from uniform deposition of normal wafer surfaces. The individual small region statistical comparison scheme then proceeds to the testing wafers. Experimental results show that the proposed method can effectively detect the non-uniform deposition regions on the wafer surface. The inspection time of the deposited wafers is quite compatible with the atmospheric pressure CVD time

  8. Inspection and repair technology for BMI penetrations

    International Nuclear Information System (INIS)

    Historically, United States (US) nuclear power plant inspections of the reactor vessel bottom-mounted-instrument (BMI) penetrations have been limited to visual verification via a combination of walk-downs and pressure tests. However in France, more than 18 ultrasonic examination (UT) and weld-surface visual test (VT) campaigns had been performed to inspect the BMI penetration nozzles and welds since 1992 with no observed failures through 2002. In April 2003, South Texas Project Unit 1 discovered apparent leakage from two nozzles during a bare-metal examination. Based on the French inspection experience, Framatome-ANP was selected for inspection and repair services to address the leaking nozzles. Inspection activities included ultrasonic examination of the tube, enhanced visual test and eddy current testing (ECT) of the J-groove weld, bobbin ECT and profile measurement of the tube inside, helium leak test, phased-array UT, borescope VT, and boat-sample removal with destructive metallurgical analysis. Repair activities included sealing the top portion of the penetration, cutting out the old nozzles, and welding in new nozzles. This presentation discusses BMI inspection and repair technology focused particularly on the South Texas Project experience. (authors)

  9. Underwater inspection robot - AIRIS 21''trademark''

    International Nuclear Information System (INIS)

    Highly reliable, cost-effective and extended examination coverage are three big demands for newly developed ISI equipment. AIRIS 21 (advanced inspection system for reactor pressure vessel and internals) which is a state-of-the-art next generation device, has been developed to reply to these demands. The device can reduce the inspection cost and increase the reliability and inspection coverage. The AIRIS 21 swims in the water toward an area to be inspected and sticks to the vessel wall using two propellers. After it sticks on the wall, the spinning speed of propellers is controlled to keep the device on the wall with constant vacuum force. Then it travels on the wall freely by two driving wheels and one trip measuring wheel. This manner of new examination system is quite different from the other conventional BWR-ID systems. This new inspection system is dramatically reduced its size [W550 x L600 x H55 (mm)] and weight [13.6 (kg)] compared with conventional system, and also saves ISI from being a critical path work because it needs no special tools, such as a large crane for handling. With AIRIS 21, it is possible to perform ID inspection of RPV welds in parallel with fuel shuffling and other core activities. (orig.)

  10. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007

    Energy Technology Data Exchange (ETDEWEB)

    West, B; Ruel Waltz, R

    2008-06-05

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

  11. Strategies to reduce PWR inspection time

    International Nuclear Information System (INIS)

    During last few years, a constant reduction in inspection time was clearly demanded by most nuclear plant owners. This requirement has to be accomplished without any impact in inspection quality that, in general, has also to be improved. All this in a market with increasing competition that forces price reductions. Under these new demands from our customers, Tecnatom reoriented its development efforts to improve his products and services to meet this challenges. Two of our main inspection activities that have clear impact in outage duration are Steam Generator and Vessel inspections. This paper describes the improvements made in these two activities as an example of the reorientation of our development efforts with a focus on the technical improvements made on the software and robotic tools applied as in the data acquisition and analysis systems. In the Steam Generator inspections, new robots with dual guide tubes are commonly used. New eddy current instruments and software were developed to keep up with the data rates produced by the faster acquisition system. Use of automatic analysis software is also helping to improve speed while reducing cost and improving overall job quality. Production rates are close to double from the previous inspection system. (author)

  12. System and method for online inspection of turbines using an optical tube with broadspectrum mirrors

    Science.gov (United States)

    Baleine, Erwan

    2015-12-22

    An optical inspection system for nondestructive internal visual inspection and non-contact infra-red (IR) temperature monitoring of an online, operating power generation turbine. The optical inspection system includes an optical tube having a viewing port, at least one reflective mirror or a mirror array having a reflectivity spectral range from 550 nm to 20 .mu.m, and capable of continuous operation at temperatures greater than 932 degrees Fahrenheit (500 degrees Celsius), and a transparent window with high transmission within the same spectral range mounted distal the viewing port. The same optical mirror array may be used to measure selectively surface temperature of metal turbine blades in the near IR range (approximately 1 .mu.m wavelength) and of thermal barrier coated turbine blades in the long IR range (approximately 10 .mu.m wavelength).

  13. Super Phenix 1: In-service inspection of main and safety tanks weldments

    International Nuclear Information System (INIS)

    In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

  14. Promoting transparency: The Korean national inspection experience

    International Nuclear Information System (INIS)

    The Republic of Korea started the LAMA full-scope safeguards inspection with the TRIGA research reactor in 1976 when the nuclear industry was at its infancy. Over two decades of rapid economic growth was propelled by stable supply of electricity, substantially from nuclear energy. Today nearly half of the nations electricity comes from sixteen operating nuclear power plants (12 LWRs + 4 OLRs). Total number of facilities under IAEA inspection reaches 30 where the Agency conducts about 400 PDIs annually. Within the last decade, nuclear transparency in Korea has transformed into the international norm primarily from the needs of rapidly expanding domestic nuclear program. In addition, possibility of North/South mutual inspection helped initiate the national inspection regime in addition to the IAEA inspection. The Technology Center for Nuclear Control was established at KAERI in 1994 in order to maintain the nation's nuclear verification expertise in support of the Korean government. National inspections have been carried out simultaneously with the IAEA inspection since 1997 with trial facilities, and all domestic facilities are being inspected from this year. Necessary legal framework and working procedures were developed and field-tried for LWRs, OLRs, fuel fabrication plants and research reactor facilities. Although the inspection equipment and technology along with the safeguards criteria are quite similar to those of the Agency, it is essential to maintain the independent conclusion capabilities between IAEA and the national authority. Substantial improvements in the IAEA safeguards inspection goal attainments since 1997 are credited to the increasing safeguards awareness among operators and SSAC. Further work is necessary to develop the evaluation criteria based on the field inspection results to meet the national inspection goals. The Korean Government signed the Additional Protocol with IAEA on June, 1999 after much deliberation since it involves facilities

  15. 49 CFR 192.241 - Inspection and test of welds.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Inspection and test of welds. 192.241 Section 192....241 Inspection and test of welds. (a) Visual inspection of welding must be conducted by an individual... nondestructively tested or visually inspected is determined according to the standards in Section 9 of API...

  16. 7 CFR 868.32 - Who shall inspect commodities.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 7 2010-01-01 2010-01-01 false Who shall inspect commodities. 868.32 Section 868.32... FOR CERTAIN AGRICULTURAL COMMODITIES Regulations Inspection Methods and Procedures § 868.32 Who shall inspect commodities. Official commodity inspections shall be performed only by official personnel....

  17. 7 CFR 27.16 - Inspection; weighing; samples; supervision.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 2 2010-01-01 2010-01-01 false Inspection; weighing; samples; supervision. 27.16... Samples § 27.16 Inspection; weighing; samples; supervision. The inspection, weighing, and sampling of... Services Office shall be (a) under the supervision of a supervisor of cotton inspection, or (b) by or...

  18. 7 CFR 75.20 - Submitted sample inspection.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Submitted sample inspection. 75.20 Section 75.20... AND CERTIFICATION OF QUALITY OF AGRICULTURAL AND VEGETABLE SEEDS Inspection § 75.20 Submitted sample inspection. A sample inspection shall be made by testing a sample of seed submitted by an applicant...

  19. 9 CFR 355.3 - Plants eligible for inspection.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Plants eligible for inspection. 355.3... § 355.3 Plants eligible for inspection. Upon application, inspection may be granted at a plant where... plant meets with the requirements of this part. Application for Inspection, Certification,...

  20. 9 CFR 318.309 - Finished product inspection.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Finished product inspection. 318.309... Canning and Canned Products § 318.309 Finished product inspection. (a) Finished product inspections must... this section. (b)-(c) (d) Procedures for handling finished product inspections where the HACCP plan...

  1. 9 CFR 381.309 - Finished product inspection.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Finished product inspection. 381.309... Finished product inspection. (a) Finished product inspections must be handled according to: (1) A HACCP.... (b)-(c) (d) Procedures for finished product inspections where the HACCP plan for thermally...

  2. Qualification and evaluation of promising methods for early detection of defects and reduction of radiation doses to personnel performing recurrent inspections of safety-relevant piping systems; testing the performance of the potential drop method. Parts A and B. Development of belts for rapid installation of a defect monitoring and measuring field and measured potential distributions at regions of dissimilar wall thickness and dissimilar welds. - Calculated results of potential distributions at regions of dissimilar wall thickness and dissimilar welds with and without flaws, and comparison with measured results

    International Nuclear Information System (INIS)

    Under the SR 2045 and SR 2045/1 projects the tests for applying the advanced potential drop method in recurrent inspections in nuclear power plants are continued. The project is chiefly aimed at optimising and improving the early detection of defects and flaws in piping systems during the customary periodic inspection. The potential drop method which has been refined for this purpose can preferably be applied as an additional alternative in places and under conditions where it is difficult for orthodox methods to detect and monitor defects and flaws in materials. As a non-destructive method, the potential drop method is almost unrivalled when it comes to continuously monitoring indications, findings and areas of the material for crack formation and crack growth (even at service temperatures). And here it was possible to achieve an appreciable success: A potential drop measuring field is now much faster to install than before thanks to the belts developed. This is of particular advantage in areas of increased radiation levels. Moreover, comparative calculations by means of the MAFIA Finite Difference Programme have proved that the calibration and interpretation of measured values obtained from ferrite/austenite weld joints, weld joints between components of different wall thickness and intricate structures can be considerably improved by such calculations. (orig.)

  3. Scientific Opinion on the public health hazards to be covered by inspection of meat (solipeds

    Directory of Open Access Journals (Sweden)

    EFSA Panel on Biological Hazards (BIOHAZ

    2013-06-01

    Full Text Available A risk ranking process identified Trichinella spp. as the most relevant biological hazard in the context of meat inspection of domestic solipeds. Without a full and reliable soliped traceability system, it is considered that either testing all slaughtered solipeds for Trichinella spp., or inactivation meat treatments (heat or irradiation should be used to maintain the current level of safety. With regard to general aspects of current meat inspection practices, the use of manual techniques during current post-mortem soliped meat inspection may increase microbial cross-contamination, and is considered to have a detrimental effect on the microbiological status of soliped carcass meat. Therefore, the use of visual-only inspection is suggested for “non-suspect” solipeds. For chemical hazards, phenylbutazone and cadmium were ranked as being of high potential concern. Monitoring programmes for chemical hazards should be more flexible and based on the risk of occurrence, taking into account Food Chain Information (FCI, covering the specific on-farm environmental conditions and individual animal treatments, and the ranking of chemical substances, which should be regularly updated and include new hazards. Sampling, testing and intervention protocols for chemical hazards should be better integrated and should focus particularly on cadmium, phenylbutazone and priority “essential substances” approved for treatment of equine animals. Implementation and enforcement of a more robust and reliable identification system throughout the European Union is needed to improve traceability of domestic solipeds. Meat inspection is recognised as a valuable tool for surveillance and monitoring of animal health and welfare conditions. If visual only post-mortem inspection is implemented for routine slaughter, a reduction in the detection of strangles and mild cases of rhodococcosis would occur. However, this was considered unlikely to affect the overall surveillance

  4. Development of an enrichment monitor for the Portsmouth GCEP

    International Nuclear Information System (INIS)

    We have developed a gas-phase UF6 enrichment monitor for use by the International Atomic Energy Agency at the Portsmouth Gas Centrifuge Enrichment Plant. The enrichment monitoring system provides a method for effective nuclear materials accountability verification while reducing the effort for both the facility operator and the inspector. The experience with an inplant prototype monitor, the facility and operational constraints, and the constraints related to international safeguards inspection are described in terms of the impact on the monitor design

  5. Status of radiation protection in interventional radiology. Assessment of inspections in 2009 by the ASN

    International Nuclear Information System (INIS)

    This report first describes the organization of inspections performed in health institutions, indicates the inspected establishments, the types of fixed installations in interventional radiology, the use of imagery in the operating theatre, and discusses the regulatory arrangements applicable to interventional radiology (in the Public Health Code, in the Labour Code). Then, the report discusses the results of inspections regarding radiation protection in interventional radiology: application of public health code arrangements (justification, patient training in radiation protection, radiological procedures and protocols, patient dosimetry monitoring), application of Labour Code arrangements (designation of the person with expertise in radiation protection, risk assessment and delimitation of monitored and controlled areas, workstation analysis, workers' training in radiation protection, individual protection equipment, workers' dosimetric monitoring, workers' medical monitoring, radiation protection technical controls), significant events, radiation protection in operating theatre. Propositions are stated regarding the differences noticed within or between the health establishments, the methodological and organisational difficulties faced by persons with expertise in radiation protection (PCR), the need of an interdisciplinary team

  6. Surface Inspection Tool for Optical Detection of Surface Defects

    Science.gov (United States)

    Nurge, Mark; Youngquist, Robert; Dyer, Dustin

    2013-01-01

    The Space Shuttle Orbiter windows were damaged both by micrometeor impacts and by handling, and required careful inspection before they could be reused. The launch commit criteria required that no defect be deeper than a critical depth. The shuttle program used a refocus microscope to perform a quick pass/fail determination, and then followed up with mold impressions to better quantify any defect. However, the refocus microscope is slow and tedious to use due to its limited field of view, only focusing on one small area of glass at a time. Additionally, the unit is bulky and unable to be used in areas with tight access, such as defects near the window frame or on the glass inside the Orbiter due to interference with the dashboard. The surface inspection tool is a low-profile handheld instrument that provides two digital video images on a computer for monitoring surface defects. The first image is a wide-angle view to assist the user in locating defects. The second provides an enlarged view of a defect centered in the window of the first image. The focus is adjustable for each of the images. However, the enlarged view was designed to have a focal plane with a short depth. This allows the user to get a feel for the depth of different parts of the defect under inspection as the focus control is varied. A light source is also provided to illuminate the defect, precluding the need for separate lighting tools. The software provides many controls to adjust image quality, along with the ability to zoom digitally the images and to capture and store them for later processing.

  7. GASVOL 18'' gas pipeline - risk based inspection study

    Energy Technology Data Exchange (ETDEWEB)

    Bjoernoey, Ola H.; Etterdal, Birger A. [Det Norske Veritas (DNV), Oslo (Norway); Guarize, Rosimar; Oliveira, Luiz F.S. [Det Norske Veritas (DNV) (Brazil); Faertes, Denise; Dias, Ricardo [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

    2003-07-01

    This paper describes a risk based approach and inspection planning as part of the Pipeline Integrity Management (PIM) system for the 95.5 km long 18'' GASVOL gas pipeline in the South eastern region of Brazil transporting circa 5 000 000 m3 dry gas per day. Pipeline systems can be subject to several degradation mechanisms and inspection and monitoring are used to ensure system integrity. Modern pipeline regulations and codes are normally based on a core safety or risk philosophy. The detailed design requirements presented in design codes are practical interpretations established so as to fulfill these core objectives. A given pipeline, designed, constructed and installed according to a pipeline code is therefore the realization of a structure, which, along its whole length, meets the applicable safety objectives of that code. The main objective of Pipeline Integrity Management (PIM) is to control and document the integrity of the pipeline for its whole service life, and to do this in a cost-effective manner. DNV has a specific approach to RBI planning, starting with an initial qualitative assessment where pipelines and damage type are ranked according to risk and potential risk reduction by an inspection and then carried forward to a quantitative detailed assessment where the level of complexity and accuracy can vary based on availability of information and owner needs. Detailed assessment requires significant effort in data gathering. The findings are dependent upon the accuracy of the inspection data, and on DNV's interpretation of the pipeline reference system and simplifications in the inspection data reported. The following specific failure mechanisms were investigated: internal corrosion, external corrosion, third party interference, landslides and black powder. RBI planning, in general words, is a 'living process'. In order to optimize future inspections, it is essential that the analyses utilize the most recent information regarding

  8. Remote visual inspection of nuclear fuel pellets with fiber optics and video image processing

    International Nuclear Information System (INIS)

    Westinghouse Hanford Company has designed and is constructing a nuclear fuel fabrication process line for the Department of Energy. This process line includes a pellet surface inspection system that remotely inspects the cylindrical surface of nuclear fuel pellets for surface spots, flaws, or discoloration. The pellets are inspected on a 100 percent basis after pellet sintering. A feeder will deliver the pellets directly to a fiber optic inspection head. The inspection head will view one pellet surface at a time. The surface image of the pellet will be imaged to a closed-circuit color television camera (CCTV). The output signal of the CCTV will be input to a digital imaging processor that stores approximately 25 pellet images at a time. A human operator will visually examine the images of the pellet surfaces on a high resolution monitor and accept or reject the pellets based on visual standards. The operator will use a digitizing tablet to record the location of rejected pellets, which will then be automatically removed from the product stream. The system is expandable to automated disposition of the pellet surface image

  9. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

    International Nuclear Information System (INIS)

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  10. Waste Calcining Facility remote inspection report

    International Nuclear Information System (INIS)

    The purpose of the Waste Calcining Facility (WCF) remote inspections was to evaluate areas in the facility which are difficult to access due to high radiation fields. The areas inspected were the ventilation exhaust duct, waste hold cell, adsorber manifold cell, off-gas cell, calciner cell and calciner vessel. The WCF solidified acidic, high-level mixed waste generated during nuclear fuel reprocessing. Solidification was accomplished through high temperature oxidation and evaporation. Since its shutdown in 1981, the WCFs vessels, piping systems, pumps, off-gas blowers and process cells have remained contaminated. Access to the below-grade areas is limited due to contamination and high radiation fields. Each inspection technique was tested with a mock-up in a radiologically clean area before the equipment was taken to the WCF for the actual inspection. During the inspections, essential information was obtained regarding the cleanliness, structural integrity, in-leakage of ground water, indications of process leaks, indications of corrosion, radiation levels and the general condition of the cells and equipment. In general, the cells contain a great deal of dust and debris, as well as hand tools, piping and miscellaneous equipment. Although the building appears to be structurally sound, the paint is peeling to some degree in all of the cells. Cracking and spalling of the concrete walls is evident in every cell, although the east wall of the off-gas cell is the worst. The results of the completed inspections and lessons learned will be used to plan future activities for stabilization and deactivation of the facility. Remote clean-up of loose piping, hand tools, and miscellaneous debris can start immediately while information from the inspections is factored into the conceptual design for deactivating the facility

  11. Inspections Over Time: The Role of Information

    International Nuclear Information System (INIS)

    When inspections in nuclear plants are planned over time it has to be decided if the time points of all inspections are fixed at the beginning of the reference time interval, e.g. one year, or if they are fixed sequentially. In the latter case the time point for the second inspection is fixed only after the first one has been performed, the third after the second one, and so on. For that decision, not only organizational aspects have to be taken into account but also the role of information: Will the Inspectorate in the latter case be able to draw an advantage from the fact that after the first inspection it may know what the plant Operator's behaviour was so far? Vice versa, the same holds for the Operator in case he plans to start an undeclared activity in the course of the reference time interval. In this paper two general inspection schemes are analyzed: The Operator behaves sequentially in both cases, whereas the Inspectorate behaves sequentially in the one, and non-sequentially in the other case. It is shown that both schemes lead to the same optimal expected detection time which means that the Inspectorate may do what is easier from organizational and financial points of view. These results are discussed from the point of view of information which both parties may gain in the course of the inspection over time. With some care the essential arguments may also be applied to more complicated, i.e. realistic inspection schemes which cannot be analyzed quantitatively until now. (author)

  12. Inspection philosophy at Barsebaeck nuclear power plant in Sweden

    International Nuclear Information System (INIS)

    At Barsebaeck nuclear power plant (2 Boiling Water Reactor Units each of 600 MW) different inspection cycles are operated in order to shorten the inspection time. The 12/24 month operating philosophy means that, alternating each year, for one unit a long inspection period of 4 weeks duration is provided for. For the other unit only a short inspection of 2 weeks is undertaken. A data-controlled information system assists the personnel in the planning and execution of the inspections. (orig.)

  13. Assessing the Technical Condition of Inspected Vehicles in Reporting Period

    OpenAIRE

    Angelovič Michal; Szabó Mário; Majdan Radoslav; Polonec Tomáš

    2014-01-01

    Vehicle emissions inspection represents a fast, relatively efective in terms of time and cost, and mainly comprehensive estimation of vehicle emissions. Procedurally, emissions inspection includes those inspection operations that focus not only on analysing exhaust gases but also on detecting the functionality and tightness of other engine components directly afecting the ecological friendliness of inspected vehicle‘s engine. Our study describes the results of vehicles inspected at an emissio...

  14. Optimal Strategy for Inspection and Repair of Structural Systems

    DEFF Research Database (Denmark)

    Thoft-Christensen, Palle; Sørensen, John Dalsgaard

    1987-01-01

    A new strategy for inspection and repair of structural elements and systems is presented. The total cost of inspection and repair is minimized with the constraints that the reliability of elements and/or of the structural system are acceptable. The design variables are the time intervals between...... inspections and the quality of the inspections. Numerical examples are presented to illustrate the performance of the strategy. The strategy can be used for any engineering system where inspection and repair are required....

  15. Development of an automated remote inspection system for the interior of the primary containment vessel of a nuclear power plant

    International Nuclear Information System (INIS)

    An automated remote inspection system has been developed for the interior of the primary containment vessel of a nuclear power plant. This system consists of an inspection robot and an operator's console. The inspection robot travels along a monorail provided in the interior of the primary containment vessel. The operator's console is located in the central control room of the power plant. We have made efforts to downsize the robot and automate the inspection and monitoring machinery. As for downsizing the robot, a 152 mm wide, 290 mm high cross-sectional area and 15 kg weight can be realized using commercially available small sensors and rearranging the parts in those sensors. As for automating the inspection and monitoring, several monitoring functions are developed using image processing, frequency analysis and other techniques applied to signals from sensors such as an ITV camera, an infrared camera and a microphone, which are mounted on the robot. Endurance tests show resistance of the robot to radiational and thermal conditions is adequate for actual use in actual power plants. (author)

  16. On results of 4th regular inspection of No.2 plant in Hamaoka Nuclear Power Station

    International Nuclear Information System (INIS)

    The 4th regular inspection of No.2 plant in Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was carried out from January 10 to May 13, 1983. The objects of inspection were the reactor, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, abandonment facilities, reactor containment equipment and emergency standby power generation facilities. The inspection of the appearance, disassembling, leak, function, performance and so on was carried out, but abnormality was not found at all. The works related to this regular inspection were executed within the range of allowable dose based on the laws. A radiation monitor for the drain sump in the containment vessel and a continuous monitor for the seawater drain sump in the turbine building were installed. Pumps were additionally installed for the drain sumps without spare pumps, and a part of the small piping for the turbine was changed to corrosion resistant STPA 23. Abnormality was not found in the internal radiation exposure of 6418 workers. (Kako, I.)

  17. Pre-service inspection and in-service inspection in Japan

    International Nuclear Information System (INIS)

    To ensure the safety of nuclear power plant, pre-service inspection/in-service inspection (PSI/ISI) has an important role, and informations obtained from various inspections during plant shut-down period are contributing to establish effective preventive maintenance activities for plant facilities. It might be said that the high level of availability of Japanese light-water nuclear power plants in these two or three years has been achieved by those efforts. In case of Japan, inspections to be carried out during scheduled plant shut-down period are not limited to code requirements but include many other inspections which are mostly reflected from troubles experienced in both domestic and overseas plants. Usually, those additional inspections are performed by Ministry of Trade and Industries' (MITI's) regulator and/or tentative requirement and considered as ISI in broad meaning. To achieve high availability of plant, it is essential to avoid unscheduled shut-down and to shorten inspection period. The developments of new technology to perform effective ISI for operating plants are continued, but on the other hand it is also very important to pay a great consideration to inspectability of the plants at the stage of plant engineering. With the leadership of MITI, improvement and standardization of light-water nuclear power plant has been proceeded and newly constructed plants have great advantage from the point of view on ISI

  18. Nuclear Technology. Course 30: Mechanical Inspection. Module 30-6, Protective Coating Inspection.

    Science.gov (United States)

    Espy, John

    This sixth in a series of eight modules for a course titled Mechanical Inspection describes the duties of the nuclear quality assurance/quality control technician that are associated with protective coatings, and the national standards that govern the selection, application, and inspection of protective coatings for the reactor containment…

  19. Research progress of terahertz wave technology in food inspection

    Science.gov (United States)

    Yan, Zhanke; Ying, Yibin; Zhang, Hongjian; Yu, Haiyan

    2006-10-01

    Food safety and quality concern have become more and more significant in recent years. There is therefore an increasing focus on new technologies that can be applied to food quality evaluation or safety inspection, either to simplify or speed up the checking process, or to provide additional functionality. For example, the technique of near infrared (NIR) spectroscopy has been used for the authentication of agricultural products and food samples. Terahertz (THz) radiation, or THz wave, is electromagnetic wave lies between mid-infrared and microwave radiation. During the past decade, THz waves have been used to characterize the electronic, vibrational and compositional properties of solid, liquid and gas phase materials. The main two applications in which THz fields involved are THz spectroscopy and THz imaging. Terahertz wave technology, as a new area of research, has shown its wide prospects in imaging, diagnosis, detection, and monitoring, etc. Recently, THz technology has gained a lot of attention from biological spectral analysis to bio-medical imaging due to its unique features compared with microwave and optical waves. In this paper, a brief review is given to summarize the progress of THz techqiues in the field of food inspection. The properties of THz wave, its uniqueness in sensing and imaging applications, and the prospect of this novel technology in food industry were discussed.

  20. Natural Gas Vehicle Cylinder Safety, Training and Inspection Project

    Energy Technology Data Exchange (ETDEWEB)

    Hank Seiff

    2008-12-31

    Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

  1. Eye Model for Inspecting the Image Quality of IOLs

    Institute of Scientific and Technical Information of China (English)

    Zhenping Huang; Renfeng Xu; Chunyan Xue; Yong Wu; Huachun Wang; Degao Zhao

    2007-01-01

    Purpose: To inspect and compare the image quality of an aspheric intraocular lens (IQ, Alcon) with those of conventional monofocal silicone and acrylic intraocular lens and multifocal intraocular lens (Array).Methods: The IOLs were tested in the eye model, which was designed to be optically equivalent to the theoretical eye model. The eye model is a combination of a spherical photographic lens with 35 mm focal length (IOL put in a water cell) and a charge coupled device (CCD) camera. The images constructed by the lenses are observed on a monitor of personal computer and the contrasts of the images are analyzed by using commercial image processing software. SHARP value is used to measure and estimate image definition.Results: The images constructed by changing the diameter of aperture stop and IOL. Observed by this eye model, the image definition of aspheric intraocular lens (IQ, Alcon) is better than others.Discussion: The proposed eye model is useful for testing functional vision and for inspecting the differences of intraocular lens.

  2. Inservice inspections for structural integrity of structures, systems, and components

    International Nuclear Information System (INIS)

    Monitoring of facility systems and equipment through predictive means such as inservice inspections is an important part of Aging Management and the demonstration of structural integrity. The primary objective of an Inservice Inspection (ISI) Program is to ensure the continued integrity and operability of important systems and components throughout their service lifetimes. DOE facilities are designed for a wide array of service conditions and environments. Each facility faces unique challenges against which an ISI program must provide a high level of confidence of integrity. For the purpose of this paper an ISI program is defined as all planned periodic examinations, tests, observations, measurements and analysis performed on structures, systems, and components, including their supports to detect material aging (degradation) and analyze its effect(s) on facility performance, safety or reliability. Formal ISI programs provide the capability to trend material and component performance versus predicted Design and Operations parameters. ISI also provides the facility a means to identify and resolve material aging problems unique to the facility in a cost effective manner. In addition ISI provides the necessary information required for cost benefit decision models to determine continued or extended service as referenced in DOE Order 4320.2, 'Capital Asset Management Process'

  3. 130-nm reticle inspection using multibeam UV-wavelength database inspection

    Science.gov (United States)

    Aquino, Christopher M.; Schlaffer, Robert

    2002-07-01

    The TeraStar family of reticle inspection systems were introduced in 2000 with die-to-die and STARlightT capability. These tools set the standard for high-resolution reticle inspection for the 130 nm design rule and below. The latest addition to the TeraStar family is the TeraStar SLF77, which extends the tool platform to include die-to-database inspection capability. Sensitivity for Chrome on Glass is 100 nm with much greater tolerance for inspecting aggressive OPC features such as serifs and assist lines. Many advanced reticles that are not inspectable on previous generation inspection tools are all inspectable on the TeraStar SLF77. Data prep times and file structure have been significantly improved with the average prep time being less than 10 percent of the 365UV-HR and average output file size less than 25 percent of the GigaPrep. The TeraStar SLF77 incorporates all the features of the TeraStar family such as triple-beam optics and TeraPro HP High Productivity Modes with the ability to run STARlight inspections concurrently with either die-to-die or die-to-database pattern inspections. Advanced registration algorithms accommodate subtle plate and machine errors to provide high sensitivity with low false detections. Advanced image overlay inspects small lines and OPC features and is very independent of defect shape and location. The TeraStar SLF77 has removed the barriers that existed with previous generation database inspection tools and made advanced reticle die-to-database inspection cost effective. Last October, KLA-Tencor introduced the TeraStar SLF77 and the three beta sites have recently completed beta evaluation. Here we present the first results from the use of the TeraStar in a production environment triple beam die-to-database inspection system. We have also shipped more than ten systems to customers worldwide. This paper describes the implementation of productivity improvements at the beta sites, performance on 130nm node customer product reticles

  4. Preventing failures by in-service inspection

    International Nuclear Information System (INIS)

    The concept of defence in depth is fundamental to the safety of nuclear installations. Defence in depth consists in a hierarchical deployment of different levels of equipment and procedures in order to maintain the effectiveness of physical barriers placed between radioactive material and workers, the public or environment in normal operation, anticipated operational occurrences and in accidents at the plant. The primary way of preventing accidents is to achieve a high quality in design, construction and operation of the plant, and thereby to ensure that deviations from normal operation are infrequent. According to international guidance on defence in depth design relies on deterministic assumptions and procedures without explicit consideration of probabilities. Conservatism, including safety margins, is a basic prerequisite, which apply to the first three level of the defence. In-service inspection and testing are important means on the second level to prevent incidents and accidents by detecting any degradation of components and equipment before it can affect the safety of the plant. Moreover, in-service inspection and testing of structures, systems and components important to safety need to be of such a standard and frequency as to ensure that levels of reliability and effectiveness remain in accordance with the design assumptions and intent, and that the safety of the plant has not been compromised since beginning of operation. The basic purpose of an in-service inspection programme is to decrease the plant risk by decreasing the probability of failure, inspection having obviously no impact on the consequences of a failure. Development of in-service inspection strategies for passive components in nuclear power plants has always involved implied, but un-quantified, risk assessments. In the early inservice inspection strategies components were consequence ranked by a safety or quality grade classification system. In these strategies influential factors for

  5. 40 CFR 63.1383 - Monitoring requirements.

    Science.gov (United States)

    2010-07-01

    ... parameter(s), such as secondary voltage of each electrical field, to be monitored and the minimum and/or... following: (i) Inspect all burners, pilot assemblies, and pilot sensing devices for proper operation and... centimeters (18 to 24 inches) above the surface of the molten glass in a cold top electric furnace that...

  6. Monitoring of the Phenix reactor conic shell

    International Nuclear Information System (INIS)

    The Safety Authority (DSIN) asked the monitoring of Phenix reactor core support structures. In this framework the cea developed a method to control by ultrasonic testing the welded joints of the core support shell, in stainless steel-316L, immersed in sodium. The method and the inspection are presented in this paper. (A.L.B.)

  7. Analysis of facility-monitoring data

    Energy Technology Data Exchange (ETDEWEB)

    Howell, J.A.

    1996-09-01

    This paper discusses techniques for analysis of data collected from nuclear-safeguards facility-monitoring systems. These methods can process information gathered from sensors and make interpretations that are in the best interests of the facility or agency, thereby enhancing safeguards while shortening inspection time.

  8. Post-Closure Inspection Letter Report for Corrective Action Unit 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, Revision 0, January 2007

    International Nuclear Information System (INIS)

    This letter selves as the post closure monitoring letter report for the above CAU for the period October 2005 - September 2006. Quarterly inspections were conducted on December 12,2005, on March 23, 2006, on June 20,2006, and on September 19,2006, to observe the condition of the gate, use-restriction warning signs, monuments, fencing, trenches, soil covers, and monitoring well covers. The first inspection was conducted on December 12, 2005. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The second inspection was conducted on March 23, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The third inspection was conducted on June 20, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended. The fourth inspection was conducted on September 19, 2006. Signs, fencing, riprap, monuments, and monitoring well covers were in excellent condition. No cracking, erosion, or subsidence was observed on the covers. No issues or concerns were identified, and no corrective actions were recommended

  9. Organization of inspection of bubble chamber photographs

    International Nuclear Information System (INIS)

    A program for inspection of bubble chamber photographs is described. The program was developed for a DEC-10 computer and is designed for PUOS-2M and PUOS-4 semiautomatic inspection and measuring projectors. Formalization of the inspection procedure allows it to be used for various physics experiments. As an example the authors consider the problem of the physical inspection in an experiment on scattering of kaons plus with momenta of 70 GeV/c by protons performed in a BEBC chamber. Primary vertices were analyzed in the following cases: low quality of reconstruction of parameters in the geometric program; lack of agreement of the number of reconstructed tracks with that indicated by inspection; and unmeasured events and events with candidate tracks for identification of proton tracks by degree of ionization. The performance of the program in these cases is evaluated. The program has been used to process 50,000 events recorded with a BEBC chamber as well as experiments recorded with the SCAT chamber and the European Hybrid Spectrometer using the RCBC, LEBC and HOLEBC chambers

  10. Remote inspection system for hazardous sites

    Energy Technology Data Exchange (ETDEWEB)

    Redd, J.; Borst, C.; Volz, R.A.; Everett, L.J. [Texas A and M Univ., College Station, TX (United States). Computer Science Dept.

    1999-04-01

    Long term storage of special nuclear materials poses a number of problems. One of these is a need to inspect the items being stored from time to time. Yet the environment is hostile to man, with significant radiation exposure resulting from prolonged presence in the storage facility. This paper describes research to provide a remote inspection capability, which could lead to eliminating the need for humans to enter a nuclear storage facility. While there are many ways in which an RI system might be created, this paper describes the development of a prototype remote inspection system, which utilizes virtual reality technology along with robotics. The purpose of this system is to allow the operator to establish a safe and realistic telepresence in a remote environment. In addition, it was desired that the user interface for the system be as intuitive to use as possible, thus eliminating the need for extensive training. The goal of this system is to provide a robotic platform with two cameras, which are capable of providing accurate and reliable stereographic images of the remote environment. One application for the system is that it might be driven down the corridors of a nuclear storage facility and utilized to inspect the drums inside, all without the need for physical human presence. Thus, it is not a true virtual reality system providing simulated graphics, but rather an augmented reality system, which performs remote inspection of an existing, real environment.

  11. Vehicle mobile 60Co container inspection system

    International Nuclear Information System (INIS)

    This paper presents a mobile 60Co container inspection system (CIS) and its performance. With all devices including industrial 60Co source, high sensitive gas-ionized array detector, image treatment and control system, inspection driving device on a vehicle, the vehicle mobile CIS has advantages of high agility and climate resistance, and it can complete emergent inspection. The mobile CIS contains equipment-vehicle and control-vehicle. Equipment-vehicle and object-container are still, while a folding detector gantry is moving through a folding rail on the equipment-vehicle and completes the inspection. the mobile CIS has the inspection characteristics similar to the fixed system and it can be used in worse circumstances. Its CI (Contrast Indicator) and IQI (Image Quality Indicator) for 100 mm steel plate attain to 0.5% and 2.5% respectively, and the SP (Space Penetration) is about 240 mm (Fe). Maximum dose per scanning is about 5 μGy, scanning speed is varied from 6 to 18 m/min, and maximum transformational speed is 90 km/h

  12. Remote inspection system for hazardous sites

    International Nuclear Information System (INIS)

    Long term storage of special nuclear materials poses a number of problems. One of these is a need to inspect the items being stored from time to time. Yet the environment is hostile to man, with significant radiation exposure resulting from prolonged presence in the storage facility. This paper describes research to provide a remote inspection capability, which could lead to eliminating the need for humans to enter a nuclear storage facility. While there are many ways in which an RI system might be created, this paper describes the development of a prototype remote inspection system, which utilizes virtual reality technology along with robotics. The purpose of this system is to allow the operator to establish a safe and realistic telepresence in a remote environment. In addition, it was desired that the user interface for the system be as intuitive to use as possible, thus eliminating the need for extensive training. The goal of this system is to provide a robotic platform with two cameras, which are capable of providing accurate and reliable stereographic images of the remote environment. One application for the system is that it might be driven down the corridors of a nuclear storage facility and utilized to inspect the drums inside, all without the need for physical human presence. Thus, it is not a true virtual reality system providing simulated graphics, but rather an augmented reality system, which performs remote inspection of an existing, real environment

  13. Wire-bond inspection in IC assembly

    Science.gov (United States)

    Rajeswari, Mandava; Rodd, Mike G.

    1996-02-01

    Wire-bonding in IC assembly process involves making a physical connection between the IC 'die' and the 'lead' by bonding wires between the two. Inspection of wire-bond quality is a' highly labor-intensive process and currently efforts are being made to automate it. This paper presents the results of a research conducted into developing a comprehensive automated wire- bond visual inspection system that is capable of performing final accept/reject inspection, providing on-line process feedback, and assisting in process validation. The proposed inspection system consists of the inspection of the bond on a bond pad, the bond on a lead and the inter-connecting wire between a bond pad and its corresponding lead. The algorithms are based on simple and easily extractable features that ensure achieving the desired accuracy and speed. A novel but simple illumination system is proposed to obtain the images of the inter- connecting wires. The proposed system is validated using several state-of-the-art IC samples. This work is sponsored by the Ministry of Science Technology and Environment, Malaysia and Intel Technology Pvt. Ltd., Malaysia.

  14. Licensing and inspection of industrial radiography in Sudan

    International Nuclear Information System (INIS)

    The use of radioisotopes in Sudan started in 1965 in the medical field, and gradually expanded in agriculture, animal research, hydrology and recently industry. During the last 4 years oil industry in Sudan became one of the biggest activity. Almost 11 foreign companies are involved in oil industry including exploration, establishment of refineries and construction of pipelines. Sudan's pipeline is the longest in Africa, about 1600 Km. The estimated number of radiation workers in these Companies are 100, some of them are locals. The country Regulatory Authority is Sudan Atomic Energy Commission (SAEC). The Commission provides personal monitoring services to all radiation workers in the country. Only about 20% of the radiation workers in these companies are under monitoring services. The total number of registered sources about 500. Number of sources used in the industrial applications of about 40% of the inventory. SAEC has difficulties in controlling the industrial radiography in the country. These difficulties can be summarized as follows: a. Difficulties in pertaining information provided by the Companies, which include: not all sources used by companies are licensed and registered; not all workers are under personal monitoring services; no notification system available by the companies to the regulatory authority in case of accidents; not enough information available by the companies to SAEC regarding the radiation work done by them (transparency). b. Poor communications with the companies. c. Resources constrains: Not enough resources for inspection missions (means of transportation). (author)

  15. Implementation of electromagnetic acoustic resonance in pipe inspection

    International Nuclear Information System (INIS)

    Electromagnetic acoustic resonance (EMAR) provides accurate and stable evaluation. Its capability has been demonstrated through online monitoring using a large-scale corrosion test loop operating at high temperature. This study uses EMAR to evaluate the thickness of pipes in a nuclear power plant during its shutdown through signal processing based on superposition of nth compression. Sections of piping evaluated with EMAR include those in long-term service, where thinning may produce scale-like surfaces, and those having complicated geometry. Moreover, we compare measurement results obtained with EMAR and with ultrasonic testing (UT). The accuracy of EMAR depends on the pipe geometry, such as the pipe diameter and whether the pipe is straight or an elbow, the presence of welding, and complicated wall thinning. We consider the causes of the difference in thickness values between EMAR measurements and UT. Finally, we discuss how to implement EMAR in pipe inspection. (author)

  16. Post-Closure Inspection Report for Corrective Action Unit 426: Cactus Spring Waste Trenches Tonopah Test Range, Nevada Calendar Year 2000; TOPICAL

    International Nuclear Information System (INIS)

    Post-closure monitoring requirements for the Cactus Spring Waste Trenches (Corrective Action Unit[CAW 426]) (Figure 1) are described in Closure Report for corrective Action Unit 426, Cactus Spring Waste Trenches. Tonopah Test Range, Nevada, report number DOE/NV-226. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on August 14, 1998. Permeability results of soils adjacent to the engineered cover and a request for closure of CAU 404 were transmitted to the NDEP on April 29, 1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on May 13, 1999. Post-closure monitoring at CAU 426 consists of the following: (1) Site inspections done twice a year to evaluate the condition of the unit; (2) Verification that the site is secure; (3) Notice of any subsidence or deficiencies that may compromise the integrity of the unit; (4) Remedy of any deficiencies within 90 days of discovery; and (5) Preparation and submittal of an annual report. Site inspections were conducted on June 19, 2000, and November 21, 2000. All inspections were made after NDEP approval of the CR, and were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of the inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are found in Attachment C

  17. Post-Closure Inspection Report for Corrective Action Unit 453: Area 9 UXO Landfill Tonopah Test Range, Nevada, Calendar Year 2001; TOPICAL

    International Nuclear Information System (INIS)

    Post-closure monitoring requirements for the Area 9 Unexploded Ordinance Landfill (Corrective Action Unit[CAU] 453) (Figure 1) are described in Closure Report for Corrective Action Unit 453: Area 9 UXO Landfill, Tonopah Test Range, Nevada, report number DOE/NV-284, August 1999. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on August 5 , 1999. The CR (containing the Post-Closure Monitoring Plan) was approved by the NDEP on September 10,1999. As stated in Section 5.0 of the NDEP-approved CR, post-closure monitoring at CAU 453 consists of the following: (1) Visual site inspections are conducted twice a year to evaluate the condition of the cover. (2) Verification that the site is secure and the condition of the fence and posted warning signs. (3) Notice of any subsidence, erosion, unauthorized excavation, etc., deficiencies that may compromise the integrity of the unit. (4) Remedy of any deficiencies within 90 days of discovery. (5) Preparation and submittal of an annual report. Site inspections were conducted on May 15, 2001 and November 6, 2001. Both site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of the inspection checklists, photographs, recommendations, and conclusions. The Post-Closure Inspection Checklists are found in Attachment A, a copy of the field notes is found in Attachment B, and inspection photographs are found in Attachment C

  18. Remote monitoring and its implication in Korea

    International Nuclear Information System (INIS)

    Remote monitoring was introduced to safeguards as a new technology under the IAEA Programme 93+2. Since then, through field trials of the IAEA and the IRMP (International Remote Monitoring Program), remote monitoring is gaining acceptance in real use of implementation. An inspection regime with containment and surveillance working in remote data transfer mode was recommended by the working group with the IAEA to seek more efficient and effective ways of safeguards implementation on PWRs as enhanced cooperation. It was implemented to combine existing digital surveillance and seals with a connection of a transmission line without much additional cost which is borne by Korea. It can reduce inspection efforts and cost maintaining current inspection quality. Three reactors are under operation as trial run for nation wide application with satisfactory results so far with incurrence of transmission cost. A virtual private network (VPN) which uses a public network is under consideration as an alternative to current telephone lines to optimize cost effectiveness of transmission. Remote monitoring is the backbone for enhanced cooperation to share safeguards efforts of the IAEA and Korea. The future of remote monitoring is closely dependent on Integrated Safeguards (IS). The current scheme of IS for LWRs without MOX is to relax current criteria, especially surveillance. As one of the nations with an active nuclear program, it is expected to maintain a skeleton of remote monitoring under IS with a closer relationship to the IAEA. (author)

  19. In-service inspection of the HANARO core components

    International Nuclear Information System (INIS)

    The inner shell of the reflector vessel surrounding the core is the most critical part from the viewpoint of a neutron irradiation. The neutron irradiation embrittles the reflector vessel and induces its dimensional change. The periodic measurement of the dimensional changes in the vertical straightness of the inner shell should be considered as one of the in-service inspections. According to an analysis, it was estimated that the inner shell would deform by a maximum of 0.84 mm toward the core center due to creep and swelling during a reactor operation period of 20 years. Even though the inner shell was properly designed and fabricated adequately to meet the design limits, this deformation should be checked by 10 year period in-service inspection to confirm not only the structural integrity but also the physical clearance with the neighboring fuel channels and control and shutoff rods. The periodical dimensional measurement of the inner shell, control rods and its related guide tubes are the main in-service inspections of the core components to confirm the structural integrity and the operation clearances. The thorough measurement of the straightness of the inner shell in August 2004, which was the first measurement after 9 years of reactor operation, showed a deformation of a maximum of 0.26 mm toward the core center which is much smaller than the prediction of the original design analysis. The control absorber or shutoff rod moving up and down is guided by two guide tubes, i. e. a shroud tube at the top and a flow tube at the bottom of their pass. The potential change of the clearance between an absorber rod and its guide tubes is also one of the important developments to consider for ensuring the safe insertion of the absorber rod into the core, as the diameters of the absorber rod and its related guide tubes could change due to neutron bombardment. Therefore their physical dimensions should be monitored periodically to confirm a certain clearances as necessary

  20. Control of trichinellosis by inspection and farm management practices.

    Science.gov (United States)

    van Knapen, F

    2000-12-01

    The prevention of human trichinellosis by proper meat inspection is a classic example of successful veterinary public health measures. The microscopic methods which have been used for more than a century to test pigs for trichinae were intended to prevent human disease. However, the value of these relatively insensitive direct detection methods, including trichinoscopy and pooled sample digestion, was debated as soon as more sensitive indirect (serological) methods became available. Two issues related to testing were discussed. First, should public health authorities endeavour to prevent all infections of humans rather than simply prevent the occurrence of disease, and second, would epidemiological surveillance and monitoring of the pig population on farms not provide a better control system to prevent human infection. This latter issue is of particular importance for those countries in the world where human trichinellosis acquired from farmed animals is absent and examination of pigs at the abattoir only results in negative findings. In countries where domestic pig infections are virtually non-existent, monitoring of Trichinella infection in wildlife could also contribute to understanding the infection pressure from nature to livestock. Trichinella-free pig farming is a feasible option for controlling this zoonosis, even in endemic areas. This approach provides an opportunity to combine good veterinary practice, in order to prevent animal diseases, with the prevention of Trichinella infection. All animals with access to the environment, or animals which are fed with potentially Trichinella-infected feed (swill, carcasses) will always constitute a public health threat, and must be inspected individually at slaughter (swine, horses, wild boars). Finally, it is important to recognize that trichinellosis is a world-wide problem that needs continuous public health attention. If no control system exists, for whatever reason, the public should be educated not to consume