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.

High throughput, parallel scanning probe microscope for nanometrology and nanopatterning applications

NARCIS (Netherlands)

Sadeghian Marnani, H.; Paul, P.C.; Herfst, R.W.; Dekker, A.; Winters, J.; Maturova, K.

2017-01-01

Scanning Probe microscope (SPM) is an important nanoinstrument for several applications such as bioresearch, metrology, inspection and nanopatterning. Single SPM is associated with relatively slow rate of scanning and low throughput measurement, thus not being suitable for scanning large samples

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

International Nuclear Information System (INIS)

McMaster, B.W.; Jones, S.B.; Sitzler, J.L.

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

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.

Computational framework for risk-based planning of inspections, maintenance, and condition monitoring using discrete Bayesian networks

DEFF Research Database (Denmark)

Nielsen, Jannie Sønderkær; Sørensen, John Dalsgaard

2018-01-01

This paper presents a computational framework for risk-based planning of inspections and repairs for deteriorating components. Two distinct types of decision rules are used to model decisions: simple decision rules that depend on constants or observed variables (e.g. inspection outcome...... expecte d life-cycle costs. For advanced decision rules, simulations are performed to estimate the expected costs, and dBNs are used within the simulations for decision-making. Information from inspections and condition monitoring are included if available. An example in the paper demonstrates...... the framework and the implemented strategies and decision rules, including various types of condition-based maintenance. The strategies using advanced decision rules lead to reduced costs compared to the simple decision rules when condition monitoring is applied, and the value of condition monitoring...

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.

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

International Nuclear Information System (INIS)

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

15. Internal symposium on recent progress of nondestructive inspection and monitoring technologies for nuclear power plants

International Nuclear Information System (INIS)

1994-01-01

At the symposium, lectures were given on the recent development of the nondestructive inspection technology for nuclear power plants, the trend regarding the nondestructive inspection in foreign countries (Japan-Germany atomic energy seminar), the present state and subjects of the monitoring technology in BWR plants, the present state and subjects of the monitoring technology in PWR plants, and the present state and the subjects for hereafter of the defect evaluation method in the equipment of light water reactors. The data on the ultrasonic flaw detection in aluminum alloy welded joints were obtained. The German inspection technology is similar to that in Japan and other countries. The research on the plant synthetic monitoring and diagnosis system is reported. The monitoring systems for abnormal state in operation, troubles and the secular change of equipment are reported. The evaluation of the flaws in nuclear piping is reported. The summaries of the lectures are collected in this book. (K.I.)

Information-Driven Inspections

International Nuclear Information System (INIS)

Laughter, Mark D.; Whitaker, J. Michael; Lockwood, Dunbar

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

Inspection of Piezoceramic Transducers Used for Structural Health Monitoring

Directory of Open Access Journals (Sweden)

Inka Mueller

2017-01-01

Full Text Available The use of piezoelectric wafer active sensors (PWAS for structural health monitoring (SHM purposes is state of the art for acousto-ultrasonic-based methods. For system reliability, detailed information about the PWAS itself is necessary. This paper gives an overview on frequent PWAS faults and presents the effects of these faults on the wave propagation, used for active acousto-ultrasonics-based SHM. The analysis of the wave field is based on velocity measurements using a laser Doppler vibrometer (LDV. New and established methods of PWAS inspection are explained in detail, listing advantages and disadvantages. The electro-mechanical impedance spectrum as basis for these methods is discussed for different sensor faults. This way this contribution focuses on a detailed analysis of PWAS and the need of their inspection for an increased reliability of SHM systems.

Design and accomplishment for the monitoring unit of the sup 6 sup 0 Co train freight inspection system

CERN Document Server

Cong Peng

2002-01-01

The sup 6 sup 0 Co railway cargo inspection system has super automaticity. And the monitoring unit is an important part of the automatic control system. The author introduces the idea of designing the monitoring unit in detail and accomplishes a new-style unit which is different from the traditional one. The monitoring unit which is highly integrated, easy to be mounted and debugged and convenient to be operated and maintained has play an excellent role in the work of the whole inspection system

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

DEFF Research Database (Denmark)

Marquez-Dominguez, Sergio

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...... 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...

Value of information in sequential decision making: Component inspection, permanent monitoring and system-level scheduling

International Nuclear Information System (INIS)

Memarzadeh, Milad; Pozzi, Matteo

2016-01-01

We illustrate how to assess the Value of Information (VoI) in sequential decision making problems modeled by Partially Observable Markov Decision Processes (POMDPs). POMDPs provide a general framework for modeling the management of infrastructure components, including operation and maintenance, when only partial or noisy observations are available; VoI is a key concept for selecting explorative actions, with application to component inspection and monitoring. Furthermore, component-level VoI can serve as an effective heuristic for assigning priorities to system-level inspection scheduling. We introduce two alternative models for the availability of information, and derive the VoI in each of those settings: the Stochastic Allocation (SA) model assumes that observations are collected with a given probability, while the Fee-based Allocation model (FA) assumes that they are available at a given cost. After presenting these models at component-level, we investigate how they perform for system-level inspection scheduling. - Highlights: • On the Value of Information in POMDPs, for optimal exploration of systems. • A method for assessing the Value of Information of permanent monitoring. • A method for allocating inspections in systems made up by parallel POMDPs.

Application of wireless LAN technology to remote monitoring for inspection equipment

International Nuclear Information System (INIS)

Ishiyama, Koichi; Kimura, Takashi; Miura, Yasushi; Yamaguchi, Katsuhiro; Kabuki, Toshihide

2011-01-01

To support inspections under an Integrated Safeguards regime into Tokai Reprocessing Plant (TRP), the IAEA suggested making use of Remote Monitoring (RM) capabilities to the inspection equipment (surveillance camera and NDA systems) installed in the spent fuel storage area at TRP. Since TRP had no pre-prepared cabling infrastructure for data transmission in the spent fuel storage area, the option of wireless LAN was chosen over the telephone line due to its lower installation costs. Feasibility studies and tests were performed by TRP on communication and particularly on long-term continuous communication using wireless LAN equipment composed of APs (AP: Access Point) and the external antennas for introducing wireless LAN technology to RM. As a result it was recognized that wireless LAN has enough ability to communicate for long periods of time and consequently the IAEA installed the AP and the external antenna to each inspection equipment and the wireless LAN technology was applied for RM. In this paper, the summary of each test and the results are reported. (author)

Central site monitoring: results from a test of accuracy in identifying trials and sites failing Food and Drug Administration inspection.

Science.gov (United States)

Lindblad, Anne S; Manukyan, Zorayr; Purohit-Sheth, Tejashri; Gensler, Gary; Okwesili, Paul; Meeker-O'Connell, Ann; Ball, Leslie; Marler, John R

2014-04-01

Site monitoring and source document verification account for 15%-30% of clinical trial costs. An alternative is to streamline site monitoring to focus on correcting trial-specific risks identified by central data monitoring. This risk-based approach could preserve or even improve the quality of clinical trial data and human subject protection compared to site monitoring focused primarily on source document verification. To determine whether a central review by statisticians using data submitted to the Food and Drug Administration (FDA) by clinical trial sponsors can identify problem sites and trials that failed FDA site inspections. An independent Analysis Center (AC) analyzed data from four anonymous new drug applications (NDAs) where FDA had performed site inspections overseen by FDA's Office of Scientific Investigations (OSI). FDA team members in the OSI chose the four NDAs from among all NDAs with data in Study Data Tabulation Model (SDTM) format. Two of the NDAs had data that OSI had deemed unreliable in support of the application after FDA site inspections identified serious data integrity problems. The other two NDAs had clinical data that OSI deemed reliable after site inspections. At the outset, the AC knew only that the experimental design specified two NDAs with significant problems. FDA gave the AC no information about which NDAs had problems, how many sites were inspected, or how many were found to have problems until after the AC analysis was complete. The AC evaluated randomization balance, enrollment patterns, study visit scheduling, variability of reported data, and last digit reference. The AC classified sites as 'High Concern', 'Moderate Concern', 'Mild Concern', or 'No Concern'. The AC correctly identified the two NDAs with data deemed unreliable by OSI. In addition, central data analysis correctly identified 5 of 6 (83%) sites for which FDA recommended rejection of data and 13 of 15 sites (87%) for which any regulatory deviations were

2016 Groundwater Monitoring and Inspection Report Gnome-Coach, New Mexico, Site January 2017

Energy Technology Data Exchange (ETDEWEB)

Kreie, Ken [USDOE Office of Legacy Management, Washington, DC (United States); Findlay, Rick [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

2017-01-01

The Gnome-Coach, New Mexico, Site was the location of an underground nuclear test in 1961 and a groundwater tracer test in 1963. Residual contamination remaining in the subsurface from these events requires long-term oversight. The Long-Term Surveillance and Maintenance Plan for the site describes the U.S. Department of Energy Office of Legacy Management’s (LM’s) plan for monitoring groundwater (radiochemical sampling and hydraulic head measurements), inspecting the site, maintaining the site’s institutional controls, evaluating and reporting data, and documenting the site’s records and data management processes. Groundwater monitoring and site inspection activities are conducted annually. This report summarizes the results of these activities conducted during the October 2015 through September 2016 reporting period. The site inspection and annual sampling were conducted on January 27, 2016. At the time of the site inspection, the signs installed near the emplacement shaft, near well USGS-1, and around the perimeter of the site were observed as being in good condition, as were the roads, wellheads, and Project Gnome monument. No new groundwater extraction wells or oil and gas wells were installed during this reporting period on the site or in the sections that surround the site. One new application was received by the New Mexico Oil Conservation Division to install a salt water disposal well approximately 0.8 miles northeast of the Project Gnome monument. The proposed well has a planned completion depth of 15,500 feet below ground surface, but as of November 2016 a drill date has not been established.

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

International Nuclear Information System (INIS)

Kikuchi, Masahiro

2010-01-01

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)

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

Technology of Inspection and Real-time Displacement Monitoring on Critical Pipe for Power Plant

Energy Technology Data Exchange (ETDEWEB)

Hyun, Jung Seob; Heo, Jae Sil [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Cho, Sun Young [KLES, Daejeon (Korea, Republic of); Heo, Jeong Yeol; Lee, Seong Kee [Korea South-East Power Co., Seoul (Korea, Republic of)

2009-10-15

High temperature steam pipes of thermal power plant are subject to a severe thermal range and usually operates well into the creep range. Cyclic operation of the plant subjects the piping system to mechanical and thermal fatigue damages. Also, poor or malfunctional supports can impose massive loads or stress onto the piping system. In order to prevent the serious damage and failure of the critical piping system, various inspection methods such as visual inspection, computational analysis and on-line piping displacement monitoring were developed. 3-dimensional piping displacement monitoring system was developed with using the aluminum alloy rod and rotary encoder sensors, this system was installed and operated on the high temperature steam piping of 'Y' thermal power plant successfully. It is expected that this study will contribute to the safety of piping system, which could minimize stress and extend the actual life of critical piping.

Incore inspection device

International Nuclear Information System (INIS)

Ogisu, Tatsuki; Taguchi, Kosei.

1995-01-01

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.)

40 CFR 63.7927 - What are my inspection and monitoring requirements for closed vent systems and control devices?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 13 2010-07-01 2010-07-01 false What are my inspection and monitoring... Pollutants: Site Remediation Closed Vent Systems and Control Devices § 63.7927 What are my inspection and... temperature at the inlet of the catalyst bed, the hourly average temperature at the outlet of the catalyst bed...

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.

78 FR 16679 - Center for Drug Evaluation and Research Medical Policy Council; Request for Comments

Science.gov (United States)

2013-03-18

... consistent, predictable communication of medical policy decisions to the public through guidance, notice and... protection, (6) bioresearch monitoring, (7) good clinical practice, (8) counter-terrorism drug development...

The international inspection of a US excess fissile material storage facility with and without remote monitoring: A cost comparison

International Nuclear Information System (INIS)

Abrams, M.; Nilsen, C.; Tolk, K.M.; McGilvary, R.C. III

1996-01-01

This study estimates the DOE-incurred costs in preparing for and hosting potential IAEA inspections of an excess pit storage facility at the Pantex Site with and without the aid of remote monitoring. Focus was on whether an investment in remote monitoring is recoverable, ie, whether the costs for installing, operating, and maintaining a remote monitoring system (RMS) are overcome by the costs that would be incurred without its use. A baseline RMS incorporating demonstrated technologies is defined and its cost estimated. This estimate and several multiples of it, together with estimates of labor and operational costs incurred under a postulated inspection regime serve as the bases of this study. A key finding is that, for the range of parameters considered, the times for investment recovery are reached relatively quickly, ie, within a decade after the inspection regime's onset. Investment recovery times, expenditures in reaching them, and average annual cost accrual rates are provided as function of RMS initial cost. A guideline indicating when investment recovery is theoretically possible is also provided

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

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

International Nuclear Information System (INIS)

2013-01-01

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 good

Review of techniques for on-line monitoring and inspection of laser welding

International Nuclear Information System (INIS)

Shao, J; Yan, Y

2005-01-01

Laser welding has been applied to various industries, in particular, automotive, aerospace and microelectronics. However, traditional off-line testing of the welds is costly and inefficient. Therefore, on-line inspection systems with low cost have being developed to increase productivity and maintain high welding quality. This paper presents the applications of acoustic, optical, visual, thermal and ultrasonic techniques and latest development of laser welding monitoring. The advantages and limitations of these techniques are also discussed

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

International Nuclear Information System (INIS)

Eom, Heung Seop; Lim, Sa Hoe; Kim, Jae Hee; Kim, Young H.; Song, Sung Jin

2005-01-01

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

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

International Nuclear Information System (INIS)

Bolton, Gary

2013-01-01

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.)

Monitor inspection device

International Nuclear Information System (INIS)

Ueshima, Yoshinobu.

1995-01-01

The device of the present invention reliably conducts monitoring by radiation monitors in a nuclear power plant thereby contributing to save the number of radiation operators and reduction of radiation exposure. Namely, radiation monitors continuously measure a plurality of γ-ray levels. A branched simultaneously counting circuit receives these signals. The output of the branched simultaneously counting circuit is inputted to a differentiation means. The differentiation means calculates a variation coefficient for each of the radiation monitoring values, namely, equivalent dose rates, and records and monitors change with time of the equivalent dose rates. With such procedures, the results of the monitoring of γ-ray levels can be judged objectively corresponding to the increase of the equivalent dose rates. As a result, the number of radiation operators can be saves and radiation exposure of the radiation operators can be reduced. (I.S.)

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

International Nuclear Information System (INIS)

Findlay, Rick

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 April 21, 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.

Proposals for in-service inspection and monitoring of selected components located within or part of the primary containment of sodium cooled fast reactors

International Nuclear Information System (INIS)

Bolt, P.R.

1976-01-01

Design and operational experience of CEGB gas cooled reactors and certain overseas reactor plant is reviewed in relation to in-service inspection and monitoring capabilities. Design guidelines and preliminary proposals are given for in-service inspection and monitoring of selected components located within or part of the primary containment of sodium cooled fast reactors. Specific comments are made on the items of further design and development work believed to be necessary

Health products inspection

International Nuclear Information System (INIS)

Stoltz, M.

2009-01-01

To protect public health, the Health Products Inspection is a public service mission where the application of regulations concerning activities on human health products and cosmetic products is verified. This mission permits a global approach to assess the health products risk-based benefit and, in monitoring by laboratory testing and by on site inspections, to verify their compliance with appropriate regulations. The seventy five inspectors perform about eight hundred inspections per year, in France and abroad. These inspections are related to data provided in the health products assessment and also to manufacturing and delivery practices. The French inspection body is also involved in the training of foreign inspectors and in the harmonization of national, European and international practices either for operators than for the competent authorities. (author)

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)

NSTec Environmental Restoration

2006-01-01

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

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.

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

International Nuclear Information System (INIS)

Boyer, Brian David; Erpenbeck, Heather H.; Miller, Karen A.; Ianakiev, Kiril D.; Reimold, Benjamin A.; Ward, Steven L.; Howell, John

2010-01-01

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 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.

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

Energy Technology Data Exchange (ETDEWEB)

None

2008-09-01

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 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

First annual report RCRA post-closure monitoring and inspections for the U-3fi waste unit. Final report, July 1995--October 1996

International Nuclear Information System (INIS)

Emer, D.F.

1997-01-01

This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi RCRA Unit, located in Area 3 of the Nevada Site (NTS), Nye County, Nevada during the July 1995 to October 1996 period. Inspections of the U-3fi RCRA Unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 420 ft ER3-3 borehole and detect changes that may be indicative of moisture movement in the regulated interval. This is the first annual report on the U-3fi closure and includes the first year baseline monitoring data as well as one quarter of compliance monitoring data

Development of automated patrol-type monitoring and inspection system for nuclear power plant and application to actual plant

International Nuclear Information System (INIS)

Senoo, Makoto; Koga, Kazunori; Hirakawa, Hiroshi; Tanaka, Keiji

1996-01-01

An automated patrol-type monitoring and inspection system was developed and applied in a nuclear power plant. This system consists of a monorail, a monitoring robot and an operator's console. The monitoring robot consists of a sensor unit and a control unit. Three kinds of sensor, a color ITV camera, an infrared camera and a microphone are installed in the sensor unit. The features of this monitoring robot are; (1) Weights 15 kg with a cross-sectional dimensions of 152 mm width and 290 mm height. (2) Several automatic monitoring functions are installed using image processing and frequency analysis for three sensor signals. (author)

Optical fiber inspection system

Science.gov (United States)

Moore, Francis W.

1987-01-01

A remote optical inspection system including an inspection head. The inspection head has a passageway through which pellets or other objects are passed. A window is provided along the passageway through which light is beamed against the objects being inspected. A plurality of lens assemblies are arranged about the window so that reflected light can be gathered and transferred to a plurality of coherent optical fiber light guides. The light guides transfer the light images to a television or other image transducer which converts the optical images into a representative electronic signal. The electronic signal can then be displayed on a signal viewer such as a television monitor for inspection by a person. A staging means can be used to support the objects for viewing through the window. Routing means can be used to direct inspected objects into appropriate exit passages for accepted or rejected objects. The inspected objects are advantageously fed in a singular manner to the staging means and routing means. The inspection system is advantageously used in an enclosure when toxic or hazardous materials are being inspected.

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. Copyright © 2014 Elsevier B.V. All rights reserved.

POST-CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 91: AREA 3 U3 fi INJECTION WELL, NEVADA TEST SITE, NEVADA FOR THE PERIOD NOVEMBER 2003 - OCTOBER 2004

International Nuclear Information System (INIS)

2005-01-01

This Post-Closure Inspection and Monitoring report provides an analysis and summary of inspections, meteorological information, and neutron soil moisture monitoring for Corrective Action Unit (CAU) 91: Area 3 U-3fi Injection Well, Nevada Test Site (NTS), Nevada. This report covers the annual period November 2003 through October 2004. Site inspections of CAU 91 are performed every six months to identify any significant changes that could impact the proper operation of the waste disposal unit. Inspection results for the current period indicate that the overall condition of the concrete pad, perimeter fence, and warning signs is good

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

International Nuclear Information System (INIS)

Peeters, M.

2006-01-01

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.

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

International Nuclear Information System (INIS)

2013-01-01

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

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

Endoscopic inspection of steam turbines

International Nuclear Information System (INIS)

Maliniemi, H.; Muukka, E.

1990-01-01

For over ten years, Imatran Voima Oy (IVO) has developed, complementary inspection methods for steam turbine condition monitoring, which can be applied both during operation and shutdown. One important method used periodically during outages is endoscopic inspection. The inspection is based on the method where the internal parts of the turbine is inspected through access borings with endoscope and where the magnified figures of the internal parts is seen on video screen. To improve inspection assurance, an image-processing based pattern recognition method for cracks has been developed for the endoscopic inspection of turbine blades. It is based on the deduction conditions derived from the crack shape. The computer gives an alarm of a crack detection and prints a simulated image of the crack, which is then checked manually

Radiation contamination monitors

International Nuclear Information System (INIS)

Kato, Tsutomu; Iba, Hiroshi; Sato, Hiroshi

1999-01-01

To make sure of no contamination on people, used articles and working uniforms coming out of the radiation controlled area, nuclear power plants are equipped with radioactive contamination monitors. This paper outlines the basic specifications and advantages of our personnel surface contamination monitors to inspect whole-body surface contamination of people coming out, article surface contamination monitors to inspect the surface and inside contamination of used articles brought out, laundry monitors to inspect surface contamination of working uniforms used in the area before and after a wash, and whole-body counters to inspect and measure the internal contamination of a person out of the area. (author)

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.

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

International Nuclear Information System (INIS)

1995-01-01

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 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

Preventing degradation and in-service inspection of NPP steam generator

International Nuclear Information System (INIS)

Ding Xunshen

1999-01-01

The author describes the degradation of steam generator tubes in initial operating stage of France NPP. The author emphatically presents the preventive measures to tackle degradation and In-service inspection of Daya Bay NPP 1 unit as a guarantee of safety operation, including secondary side water chemistry monitoring and controlling, leakage rate monitoring, eddy-current inspection, mechanical cleaning, cleanliness inspection, foreign objects removal and etc

Inspection systems for valves monitoring at EDF

International Nuclear Information System (INIS)

Germain, J.L.; Granal, L.; Provost, D.; Touillez, M.

1997-01-01

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)

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/.

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...... for this dynamic new industry. There is a need to understand the effect(s) of more advanced designs and manufacturing approaches, the prevalence and significance of production defects in material and structure, and the optimization of maintenance/inspection effort through monitoring. Described in this paper......-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...

Operation of inspection data acquisition and evaluation system

International Nuclear Information System (INIS)

Takahashi, Yoichi; Harada, Hiroshi; Watanabe, Masayuki; Sakaguchi, Makoto; Ishikawa, Masayuki

2016-01-01

Rokkasho Reprocessing Plant (RRP) is a large scale plant to treat a huge amount of Plutonium significant for safeguards. The LArge SCAle Reprocessing plant safeguards (LASCAR) Forum recommended an effective utilization of unattended verification systems and automated data acquisition system etc. Based on LASCAR recommendation, Nuclear Material Control Center (NMCC) has developed the inspection data acquisition system as the automated data acquisition system from the unattended verification systems (including non-destructive assay equipment, solution monitoring system and surveillance camera). The data gathered from the unattended verification system are provided to the inspection data evaluation system for the State and the IAEA. In this development, redundancy concepts for data transfer line, in order to prevent inspection data missing, were introduced, and the timely confirmation of solution behaver such as material flows and inventories by the solution monitoring can be achieved. Furthermore, for purpose of efficiency of evaluation of inspection activity for the State, NMCC has developed the inspection data evaluation system which operates automated partition of inspection data coming from each verification equipment. Additionally, the inspection data system evaluation can manage the inspection activities and their efforts. These development and operation have been funded by JSGO (Japan Safeguards Office). This paper describes development history and operation of the inspection data acquisition and evaluation system. (author)

POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 417: CENTRAL NEVADA TEST AREA - SURFACE, HOT CREEK VALLEY, NEVADA, FOR CALENDAR YEAR 2004

Energy Technology Data Exchange (ETDEWEB)

BECHTEL NEVADA; NNSA NEVADA SITE OFFICE

2005-04-01

This post-closure inspection and monitoring report has been prepared according to the stipulations laid out in the Closure Report (CR) for Corrective Action Unit (CAU) 417, Central Nevada Test Area (CNTA)--Surface (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office [NNSA/NV], 2001), and the Federal Facility Agreement and Consent Order (FFACO, 1996). This report provides an analysis and summary of site inspections, subsidence surveys, meteorological information, and soil moisture monitoring data for CAU 417, which is located in Hot Creek Valley, Nye County, Nevada. This report covers Calendar Year 2004. Inspections at CAU 417 are conducted quarterly to document the physical condition of the UC-1, UC-3, and UC-4 soil covers, monuments, signs, fencing, and use restricted areas. The physical condition of fencing, monuments, and signs is noted, and any unusual conditions that could impact the integrity of the covers are reported. The objective of the soil moisture monitoring program is to monitor the stability of soil moisture conditions within the upper 1.2 meters (m) (4 feet [ft]) of the UC-1 Central Mud Pit (CMP) cover and detect changes that may be indicative of moisture movement exceeding the cover design performance expectations.

Development and performance of inspection equipment for pressure tubes in Fugen

International Nuclear Information System (INIS)

Naruo, Kazuteru; Tanimoto, Ken-ichi; Ohta, Takeo; Nakamura, Takahisa; Imaizumi, Kiyoshi.

1984-01-01

The pressure tubes of Fugen are the important equipment as the many tubes compose the core, and since they are made of Zr-2.5% Nb alloy which has been used for the first time in Japan, they have become the object of monitoring (the follow-up investigation of the change of inside diameter, the presence of defects and so on) in addition to the in-service inspection. In this paper, on the inspection equipment for pressure tubes, that has been developed independently by the Power Reactor and Nuclear Fuel Development Corp. in order to carry out the ISI and monitoring, the course of development and the construction and the performance are reported, and the results of having used it for the fourth regular inspection of Fugen are described. The 10-year plan of the ISI and monitoring of pressure tubes is shown. The core of Fugen is composed of 224 pressure tubes, therefore, the inspection is carried out by sampling inspection. The monitoring is carried out on four tubes for the follow-up investigation and one tube that shows the severest operation history at the time of inspection. The equipment performs ultrasonic flaw detection, the measurement of inside diameter and the visual inspection of internal surface. (Kako, I.)

Proposal of inspection methodology for environment radiological control

International Nuclear Information System (INIS)

Martins, Nadia Soido Falcao

2005-01-01

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

Long-Range Piping Inspection by Ultrasonic Guided Waves

International Nuclear Information System (INIS)

Joo, Young Sang; Lim, Sa Hoe; Eom, Heung Seop; Kim, Jae Hee

2005-01-01

The ultrasonic guided waves are very promising for the long-range inspection of large structures because they can propagate a long distance along the structures such as plates, shells and pipes. The guided wave inspection could be utilized for an on-line monitoring technique when the transmitting and receiving transducers are positioned at a remote point on the structure. The received signal has the information about the integrity of the monitoring area between the transmitting and receiving transducers. On-line monitoring of a pipe line using an ultrasonic guided wave can detect flaws such as corrosion, erosion and fatigue cracking at an early stage and collect useful information on the flaws. However the guided wave inspection is complicated by the dispersive characteristics for guided waves. The phase and group velocities are a function of the frequency-thickness product. Therefore, the different frequency components of the guided waves will travel at different speeds and the shape of the received signal will changed as it propagates along the pipe. In this study, we analyze the propagation characteristics of guided wave modes in a small diameter pipe of nuclear power plant and select the suitable mode for a long-range inspection. And experiments will be carried out for the practical application of a long-range inspection in a 26m long pipe by using a high-power ultrasonic inspection system

In service inspection of SUPERPHENIX 1 vessels: MIR

International Nuclear Information System (INIS)

Asty, M.; Viard, J.; Lerat, B.; Saglio, R.

1985-01-01

Although no in-service inspection constraints were imposed on the Phenix vessels, the Safety Authorities asked that the design of SUPERPHENIX 1 makes it possible to monitor throughout the lifetime of the reactor, surface and internal defects on the main vessel. A pool design and the presence of heat baffles inside the main vessel make access from the inside of the vessel impossible. Thus, an inspection can only be performed from the outside of the main vessel: the distance between the walls of the main and safety vessels is such that an inspection device can be introduced into the corresponding space. As the design of the reactor precludes radiographic inspection, the method which was selected for monitoring internal defects in the main vessel is ultrasonics. However, the anisotropic structure of austenitic stainless steel welds limits the performance of this technique. The authors present the in-service inspection device, MIR, which has been specially developed for the visual and ultrasonic examination of SUPERPHENIX 1 vessels

Fully Employing Software Inspections Data

Science.gov (United States)

Shull, Forrest; Feldmann, Raimund L.; Seaman, Carolyn; Regardie, Myrna; Godfrey, Sally

2009-01-01

Software inspections provide a proven approach to quality assurance for software products of all kinds, including requirements, design, code, test plans, among others. Common to all inspections is the aim of finding and fixing defects as early as possible, and thereby providing cost savings by minimizing the amount of rework necessary later in the lifecycle. Measurement data, such as the number and type of found defects and the effort spent by the inspection team, provide not only direct feedback about the software product to the project team but are also valuable for process improvement activities. In this paper, we discuss NASA's use of software inspections and the rich set of data that has resulted. In particular, we present results from analysis of inspection data that illustrate the benefits of fully utilizing that data for process improvement at several levels. Examining such data across multiple inspections or projects allows team members to monitor and trigger cross project improvements. Such improvements may focus on the software development processes of the whole organization as well as improvements to the applied inspection process itself.

International Nuclear Safeguards Inspection Support Tool (INSIST)

International Nuclear Information System (INIS)

St. Pierre, D.E.; Steinmaus, K.L.; Moon, B.D.

1994-07-01

DOE is committed to providing technologies to the International Atomic Energy Agency (IAEA) to meet escalating monitoring and inspection requirements associated with the Non-Proliferation Treaty (NPT). One example of technology provided to the IAEA is the information management and remote monitoring capabilities being customized for the IAEA by the International Safeguards Division of the Office of Non-Proliferation and National Security. The ongoing Safeguards Information Management Systems (SIMS) program is an interlaboratory effort providing the IAEA with a range of information management capabilities designed to enhance the effectiveness of their nuclear inspection activities. The initial commitment involved the customization of computer capabilities to provide IAEA with the basic capability to geographically organize, store, and retrieve the large quantity of information involved in their nuclear on site inspection activities in Iraq. This initial system, the International Nuclear Safeguards Inspection Support Tool (INSIST), was developed by DOE's Pacific Northwest Laboratory (PNL). To date, two INSIST workstations have been deployed at the IAEA. The first has been used to support the IAEA Action Team in the inspection of Iraqi nuclear facilities since August 1993. A second, and similar, workstation has been deployed to support environmental monitoring under the IAEA 93+2 Programme. Both INSIST workstations geographically integrate analog (video) and digital data to provide an easy to use and effective tool for storing retrieving and displaying multimedia site and facility information including world-wide maps, satellite and aerial imagery, on site photography, live inspection videos, and treaty and inspection textual information. The interactive, UNIX-based workstations have a variety of peripheral devices for information input and output. INSIST software includes commercial-off-the-shelf (COTS) modules and application-specific code developed at PNL

Automatic vibration monitoring system for the diagnostic inspection of the WWER-440 type nuclear power plants

International Nuclear Information System (INIS)

Hollo, E.; Siklossy, P.; Toth, Zs.

1982-01-01

In the Hungarian Research Institute for Electric Power Industry (VEIKI) an automatic vibration monitoring system for diagnostics and inspection of nuclear power plants of type WWER-440 was developed. The paper summarizes the results of this work and investigates the use of mechanical vibrations and oscillations induced by flow for fault diagnosis. The design of the hardware system, the present software possibilities, the laboratory experiments and the guidelines for future software developments are also described in detail. (A.L.)

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

Inspection Correlation Study of Ultrasonic-Based In Situ Structural Health Monitoring Monthly Report for December 2014-January 2015

Science.gov (United States)

2015-05-01

fatigue an induced ultrasonic elastic vibration (via piezoelectric transducers [ PZTs ]) propagates through the dogbone specimen. A receiver PZT picks up...inspection of fatigue crack growth in aluminum 7075-T6 dogbone specimens. Acellent Technologies, Inc., is supporting this project through providing...January 2015. 15. SUBJECT TERMS structural health monitoring, probabilistics, fatigue damage, guided waves, Lamb waves 16. SECURITY CLASSIFICATION OF

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

International Nuclear Information System (INIS)

1995-01-01

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

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

International Nuclear Information System (INIS)

Richardson, G.

2003-01-01

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)

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.

On-Site inspections as a tool for nuclear explosion monitoring in the framework of the Comprehensive Nuclear Test Ban Treaty

Science.gov (United States)

Arndt, R.; Gaya-Pique, L.; Labak, P.; Tanaka, J.

2009-04-01

On-site inspections (OSIs) constitute the final verification measure under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). OSIs are launched to establish whether or not a nuclear explosion has been carried out, thus they are conducted to verify States' compliance with the Treaty. During such an inspection, facts are gathered within a limited investigation area of 1000 Km2 to identify possible violators of the Treaty. Time scale (referring both to the preparation of the inspection as well as to the conduct of an OSI itself) is one of the challenges that an inspection team has to face when conducting an OSI. Other challenges are the size of the team - which is limited to 40 inspectors - and political limitations imposed by the Treaty in the use of allowed techniques. The Integrated Field Exercise 2008 (IFE08) recently conducted in Kazakhstan was the first large-scale, as well as the most comprehensive, on site inspection exercise ever conducted by the Preparatory Commission of the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO). The exercise took place in a deserted area south east of Kurchatov, within the former Soviet Union's Semipalatinsk nuclear test site. In this paper we will provide an overview of the technical activities conducted by the inspection team during IFE08 in order to collect evidence for a hypothetical nuclear explosion test. The techniques applied can be distributed in four different blocks: visual observation (to look for man-made changes in the geomorphology as well as anthropogenic features related to an underground nuclear explosion, UNE); passive seismic monitoring (to identify possible aftershocks created by the UNE); radionuclide measurements (to collect evidence for radionuclide isotopes related to a nuclear explosion); and finally geophysical surveys (to identify geophysical signatures related to an UNE in terms of changes in the geological strata, to the hydrogeological regime, and in terms of the shallow remains of the

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.

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

International Nuclear Information System (INIS)

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

2005-02-01

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

Monitoring System for the Inspection of Vehicle Loads for Radioactivity

International Nuclear Information System (INIS)

Krishnamarchri, G.; Chaudhury, P.; Jain, A.; Kale, M. S.; Pradeepkumar, K. S.; Sharma, D. N.; Venkat Raj, V.

2004-01-01

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

Inspection of licensee - Maintenance programme and activities

International Nuclear Information System (INIS)

2013-01-01

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

Remotely deployable aerial inspection using tactile sensors

Science.gov (United States)

MacLeod, C. N.; Cao, J.; Pierce, S. G.; Sullivan, J. C.; Pipe, A. G.; Dobie, G.; Summan, R.

2014-02-01

For structural monitoring applications, the use of remotely deployable Non-Destructive Evaluation (NDE) inspection platforms offer many advantages, including improved accessibility, greater safety and reduced cost, when compared to traditional manual inspection techniques. The use of such platforms, previously reported by researchers at the University Strathclyde facilitates the potential for rapid scanning of large areas and volumes in hazardous locations. A common problem for both manual and remote deployment approaches lies in the intrinsic stand-off and surface coupling issues of typical NDE probes. The associated complications of these requirements are obviously significantly exacerbated when considering aerial based remote inspection and deployment, resulting in simple visual techniques being the preferred sensor payload. Researchers at Bristol Robotics Laboratory have developed biomimetic tactile sensors modelled on the facial whiskers (vibrissae) of animals such as rats and mice, with the latest sensors actively sweeping their tips across the surface in a back and forth motion. The current work reports on the design and performance of an aerial inspection platform and the suitability of tactile whisking sensors to aerial based surface monitoring applications.

Multi-Canister overpack inservice inspection and maintenance

International Nuclear Information System (INIS)

SMITH, K.E.

1998-01-01

The factors to be considered in establishing inservice inspection and maintenance requirements for the Multi-Canister Overpack (MCO) include evaluating the likelihood of degradation to the MCO pressure boundary due to erosion and corrosion, reviewing commercial practice for NRC licensed spent nuclear fuel storage systems, and examining the individual MCO components for maintenance needs. Reviews of the potential for MCO erosion and corrosion conclude that neither will pose a threat to the MCO pressure boundary. Consistent with commercial practice for spent fuel storage systems, the MCO closure weld will be helium leak tested prior to placement in interim storage. Beyond the CSB facility related monitoring plans (radiological monitoring, emissions monitoring, vault cooling data, etc.), no inservice inspection or maintenance of the MCO is required during interim storage

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

International Nuclear Information System (INIS)

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

2007-02-01

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-11-01

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.

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

International Nuclear Information System (INIS)

1980-11-01

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

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

International Nuclear Information System (INIS)

BECHTEL NEVADA

2004-01-01

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

Inspection practice and a role of TSO

International Nuclear Information System (INIS)

Janzekovic, H.

2010-01-01

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)

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

Inspection of nuclear reactor welding by acoustic emission

International Nuclear Information System (INIS)

Prine, D.W.

1977-01-01

The objective of the work described is to evaluate in-process acoustic emission weld monitoring with the goal of upgrading the inspection techniques for assuring better weld quality in nuclear reactor piping and pressure vessels. To accomplish this overall objective, the following specific goals have been set within a three year program: (1) prove the feasibility of in-process AE under shop conditions and validate the AE findings by currently acceptable NDE techniques; (2) develop and build a prototype monitor for use in Nuclear Fabrication shops; and (3) provide data for NRC/ASME acceptance of the inspection practice

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.

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

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)

NSTec Environmental Restoration

2006-01-01

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

Robotic inspection of nuclear waste storage facilities

International Nuclear Information System (INIS)

Fulbright, R.; Stephens, L.M.

1995-01-01

The University of South Carolina and the Westinghouse Savannah River Company have developed a prototype mobile robot designed to perform autonomous inspection of nuclear waste storage facilities. The Stored Waste Autonomous Mobile Inspector (SWAMI) navigates and inspects rows of nuclear waste storage drums, in isles as narrow as 34 inches with drums stacked three high on each side. SWAMI reads drum barcodes, captures drum images, and monitors floor-level radiation levels. The topics covered in this article reporting on SWAMI include the following: overall system design; typical mission scenario; barcode reader subsystem; video subsystem; radiation monitoring subsystem; position determination subsystem; onboard control system hardware; software development environment; GENISAS, a C++ library; MOSAS, an automatic code generating tool. 10 figs

A quadcopter with heterogeneous sensors for autonomous bridge inspection.

Science.gov (United States)

2014-02-01

Continuously monitoring a bridges health by sensor technologies has been widely used to maintain the operation of : a : roadwork while protecting public users safety. However, monitoring and inspecting numerous bridges in a state is a labor : -...

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

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

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

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

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

International Nuclear Information System (INIS)

1997-01-01

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

Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the period October 2000-July 2001

International Nuclear Information System (INIS)

Tobiason, D. S.

2002-01-01

This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 2000--July 2001 monitoring period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in July 2001. There has been no subsidence at any of the markers since monitoring began eight years ago. Precipitation for the period October 2000 through July 2001 was 9.42 centimeters (cm) (3.71 inches [in]) (U.S. National Weather Service, 2001). The prior year annual rainfall (January 2000 through December 2000) was 10.44 cm (4.1 1 in.). The recorded average annual rainfall for this site from 1972 to January 2000 is 14.91 cm (5.87 in.). The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that may be indicative of moisture movement at a point located directly beneath each trench. All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the trenches

Some reliability targets affecting the necessary provisions for in-service inspection and monitoring of LMFBR engineering components

International Nuclear Information System (INIS)

Bolt, P.R.

1980-01-01

The possible consequences of failure of primary and secondary sodium circuit components are discussed with particular reference to post incident fault diagnosis, remedial procedures and outage durations. The core support structures and steam generator units are identified as particularly important components in terms of economic consequence of their failure. Important safety considerations may also apply. Levels of reliability for core support and steam generator integrity, necessary to meet economic and certain safety criteria, are discussed and quantitative data is given. Possible failure and deterioration mechanisms which could result in unacceptable reductions in reliability are then identified for the core support and steam generator units. Following a consideration of the reliability targets and possible causes of loss of reliability, an appraisal is made of the necessary extent of in-service data to be obtained on component behaviour and condition. In-service inspection and monitoring methods that could be used to obtain this data are described. Consideration is given to UK and overseas inspection experience on LMFBR and other nuclear plant. (author)

Some reliability targets affecting the necessary provisions for in-service inspection and monitoring of LMFBR engineering components

Energy Technology Data Exchange (ETDEWEB)

Bolt, P R [Fast Reactor Engineering, Plant Engineering Department, CEGB, Barnwood, Gloucester (United Kingdom)

1980-11-01

The possible consequences of failure of primary and secondary sodium circuit components are discussed with particular reference to post incident fault diagnosis, remedial procedures and outage durations. The core support structures and steam generator units are identified as particularly important components in terms of economic consequence of their failure. Important safety considerations may also apply. Levels of reliability for core support and steam generator integrity, necessary to meet economic and certain safety criteria, are discussed and quantitative data is given. Possible failure and deterioration mechanisms which could result in unacceptable reductions in reliability are then identified for the core support and steam generator units. Following a consideration of the reliability targets and possible causes of loss of reliability, an appraisal is made of the necessary extent of in-service data to be obtained on component behaviour and condition. In-service inspection and monitoring methods that could be used to obtain this data are described. Consideration is given to UK and overseas inspection experience on LMFBR and other nuclear plant. (author)

Statistics and analysis of the inspection report´s modification rate

Directory of Open Access Journals (Sweden)

Xing HE

2014-08-01

Full Text Available Objective: Accordingto the statistics and regulatory inspection reports modification rate, incorporated in the hospital quality control target,together withthe strictly control and management makethe inspection results change rate up to the hospital quality management requirements. Methods: Counted upevery kind of biochemical items which were monitored by machine 7180 in the biochemical laboratory from April to October 2013, and strengthen the inspector´s sense of responsibility by the modification rate of timely rectification. Results: Every kind of biochemical items which were monitored by the machine 7180 including 62022 persons in the biochemical laboratory from April to October 2013, 896 persons´ inspection results were altered before printing ,which was 1.45 percent ;75 persons´ inspection results were altered by upper administrator after printing, which was 0.12 percent of the total and 8.37 percent of the altered people. Conclusion: Our inspection report modification rate decreased from 27.77 percent in April to 1.88 percent in October ,the percentage decreased obviously. It proved that the PDCA model was successful in inspection report modification rate of Lis in our hospital, which achieved our quality management target.

Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 91: Area 3 U-3fi Injection Well, Nevada Test Site, Nevada, for the period October 2000-October 2001

International Nuclear Information System (INIS)

Tobiason, D. S.

2002-01-01

This annual Neutron Soil Moisture Monitoring 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 2000 to October 2001 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 program is to monitor the soil moisture conditions along the 128-meter (m) (420-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) or to detect changes that may be indicative of subsidence within the disposal unit itself

Optimizing pre-service inspection data

International Nuclear Information System (INIS)

Mullins, L.E.; Harrison, J.M.

1986-01-01

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

Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor

International Nuclear Information System (INIS)

Masato Ando; Shigenobu Kubo; Yoshio Kamishima; Toru Iitsuka

2006-01-01

The objective of in-service inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-service inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-service inspection concept was developed taking these features into account. The inspection technologies were developed to implement in-service inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed. (authors)

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

International Nuclear Information System (INIS)

2010-01-01

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

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

A design condition for incorporating human judgement into monitoring systems

International Nuclear Information System (INIS)

Tanaka, K.; Klir, G.J.

1999-01-01

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

Selection of suitable NDT methods for building inspection

Science.gov (United States)

Pauzi Ismail, Mohamad

2017-11-01

Construction of modern structures requires good quality concrete with adequate strength and durability. Several accidents occurred in the civil constructions and were reported in the media. Such accidents were due to poor workmanship and lack of systematic monitoring during the constructions. In addition, water leaking and cracking in residential houses was commonly reported too. Based on these facts, monitoring the quality of concrete in structures is becoming more and more important subject. This paper describes major Non-destructive Testing (NDT) methods for evaluating structural integrity of concrete building. Some interesting findings during actual NDT inspections on site are presented. The NDT methods used are explained, compared and discussed. The suitable methods are suggested as minimum NDT methods to cover parameters required in the inspection.

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

International Nuclear Information System (INIS)

Reimann, K.J.

1980-12-01

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

A simple condition monitoring model for a direct monitoring process

NARCIS (Netherlands)

Christer, A.H.; Wang, Wenbin

1995-01-01

This paper addresses the problem of condition monitoring of a component which has available a measure of condition called wear. Wear accumulates over time and monitoring inspections are performed at chosen times to monitor and measure the cumulative wear. If past measurements of wear are available

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

International Nuclear Information System (INIS)

2008-01-01

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

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

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.

Seismic aftershock monitoring for on-site inspection purposes. Experience from Integrated Field Exercise 2008.

Science.gov (United States)

Labak, P.; Arndt, R.; Villagran, M.

2009-04-01

One of the sub-goals of the Integrated Field Experiment in 2008 (IFE08) in Kazakhstan was testing the prototype elements of the Seismic aftershock monitoring system (SAMS) for on-site inspection purposes. The task of the SAMS is to collect the facts, which should help to clarify nature of the triggering event. Therefore the SAMS has to be capable to detect and identify events as small as magnitude -2 in the inspection area size up to 1000 km2. Equipment for 30 mini-arrays and 10 3-component stations represented the field equipment of the SAMS. Each mini-array consisted of a central 3-component seismometer and 3 vertical seismometers at the distance about 100 m from the central seismometer. The mini-arrays covered approximately 80% of surrogate inspection area (IA) on the territory of former Semipalatinsk test site. Most of the stations were installed during the first four days of field operations by the seismic sub-team, which consisted of 10 seismologists. SAMS data center comprised 2 IBM Blade centers and 8 working places for data archiving, detection list production and event analysis. A prototype of SAMS software was tested. Average daily amount of collected raw data was 15-30 GB and increased according to the amount of stations entering operation. Routine manual data screening and data analyses were performed by 2-6 subteam members. Automatic screening was used for selected time intervals. Screening was performed using the Sonoview program in frequency domain and using the Geotool and Hypolines programs for screening in time domain. The screening results were merged into the master event list. The master event list served as a basis of detailed analysis of unclear events and events identified to be potentially in the IA. Detailed analysis of events to be potentially in the IA was performed by the Hypoline and Geotool programs. In addition, the Hyposimplex and Hypocenter programs were also used for localization of events. The results of analysis were integrated

Task 1. Monitoring real time materials degradation. NRC extended In-situ and real-time Monitoring

Energy Technology Data Exchange (ETDEWEB)

Bakhtiari, Sasan [Argonne National Lab. (ANL), Argonne, IL (United States)

2012-03-01

The overall objective of this project was to perform a scoping study to identify, in concert with the nuclear industry, those sensors and techniques that have the most promising commercial viability and fill a critical inspection or monitoring need. Candidates to be considered include sensors to monitor real-time material degradation, characterize residual stress, monitor and inspect component fabrication, assess radionuclide and associated chemical species concentrations in ground water and soil, characterize fuel properties, and monitor severe accident conditions. Under Task 1—Monitoring Real-Time Materials Degradation—scoping studies were conducted to assess the feasibility of potential inspection and monitoring technologies (i.e., a combination of sensors, advanced signal processing techniques, and data analysis methods) that could be utilized in LWR and/or advanced reactor applications for continuous monitoring of degradation in-situ. The goal was to identify those techniques that appear to be the most promising, i.e., those that are closest to being both technically and commercially viable and that the nuclear industry is most likely to pursue. Current limitations and associated issues that must be overcome before commercial application of certain techniques have also been addressed.

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

International Nuclear Information System (INIS)

McMaster, B.W.

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

An overview of the on-site inspection measurements from the non-proliferation experiment

Energy Technology Data Exchange (ETDEWEB)

Zucca, J.J. [Lawrence Livermore National Lab., CA (United States)

1994-12-31

An on-site inspection (OSI) is an in-person visit to site to collect data and examine evidence in order to determine the source of an ambiguous event detected via remote monitoring systems or other measures. Its purpose is to determine whether the treaty has been violated, to deter violations, and to build confidence. At the time of this writing, it is anticipated that the Comprehensive Test Ban Treaty (CTBT) being developed in the Conference on Disarmament will contain OSI provisions. In an era of testing moratoria, the Non-Proliferation Experiment (NPE) provided a unique opportunity to investigate candidate OSI techniques. On site inspections could occur in three different contexts: after-the-fact inspections based on information from remote monitoring systems; inspections prior to, during, and after large declared chemical explosions (e.g., a large mining explosion); continuous monitoring inspections with unattended sensors at certain agreed-upon sites (e.g., previous test sites). OSI monitoring techniques need to be designed to detect the phenomena and residual effects of nuclear explosions. In the underground case, the primary effects of interest for OSI are the electromagnetic pulse, shock waves, aftershocks, radioactive gas, rubble zone, and apical void. These effects are well known and the basic techniques for their detection well established. We designed our measurement program for the NPE to answer specific issues about these detection technologies. Our measurement program includes the following: zerotime electromagnetic measurements; seismic aftershock survey; before and after electrical soundings; gas tracers introduced into the explosive; before and after multispectral overhead imagery from low-flying aircraft; before and after geological surveys.

76 FR 65165 - Importation of Plants for Planting; Risk-Based Sampling and Inspection Approach and Propagative...

Science.gov (United States)

2011-10-20

..., this 14th day of October 2011. Kevin Shea, Acting Administrator, Animal and Plant Health Inspection... DEPARTMENT OF AGRICULTURE Animal and Plant Health Inspection Service [Docket No. APHIS-2011-0092] Importation of Plants for Planting; Risk-Based Sampling and Inspection Approach and Propagative Monitoring and...

Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the Period October 1999-October 2000

Energy Technology Data Exchange (ETDEWEB)

D. F. Emer

2001-03-01

This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 1999-October 2000 period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in August 2000. There has been no subsidence at any of the markers since monitoring began seven years ago. The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that maybe indicative of moisture movement at a point located directly beneath each trench. Precipitation for the period October 1999 through October 2000 was 10.44 centimeters (cm) (4.11 inches [in.]) (U.S. National Weather Service, 2000). The prior year annual rainfall (January 1999 through December 1999) was 10.13cm (3.99 in.). The highest 30-day cumulative rainfall occurred on March 8, 2000, with a total of 6.63 cm (2.61 in.). The heaviest daily precipitation occurred on February 23,2000, with a total of 1.70 cm (0.67 in.) falling in that 24-hour period. The recorded average annual rainfall for this site, from 1972 to January 1999, is 15.06 cm (5.93 in.). All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the

Review of activities relevant to in-service inspection

International Nuclear Information System (INIS)

Imanaka, N.

1980-01-01

Nuclear power plants are requested to provide continuing safety that cannot compare with other industries, as plant safety is a matter of much concern. To provide continuous assurance for plant safety there is increasing tendency to demand much of inspection of components during the lifetime. This inservice inspection of LMFBRs should be investigated from a view point of different systems and characteristics from LWRs. In this paper a review for inservice inspection of LMFBRs is described. To provide a continuous assurance of safety to the LMFBR, it is essential to develop how to construct the components to maintain the integrity throughout the service lifetime. Especially how to design is urged for this object. In-service inspection should be located only to compensate some uncertainty remained at the design stage, as it is too much complex in practice. As for inspection techniques, leak monitoring is assumed to be a best way to assure the plant safety continuously with the minimum plant outage time and minimum radioactive hazard to the inspectors

Guided wave technology for in-service inspection and online monitoring for long term operation of nuclear power plants

International Nuclear Information System (INIS)

Bertoncini, Francesco; Raugi, Marco; Cappelli, Mauro; Cordella, Francesco; Mazzini, Davide

2015-01-01

In-Service Inspection (ISI) and monitoring of all equipment (Systems, Structures and Components, SSCs) of a Nuclear Power Plant (NPP), are actions aimed at preventing failures both for economical and safety purposes. SSCs ageing due to stresses such as corrosion, load variations, flow conditions, temperature and neutron irradiation can be a potential limit for NPP life extension or operation beyond their license term (Long Term Operation. LTO). ISI has a main role on the actual possibility of LTO assuring the required safety. Guided Waves are structure-borne ultrasonic waves that propagate along the structure confined and guided by its geometric boundaries. Guided Wave Testing can find defect locations through long-range screening using low-frequency waves (from 5 to 250 kHz). The technology is regularly used for pipe testing in the oil and gas industry. In the nuclear industry, regulators are working to standardize monitoring and inspection procedures. To use the technology inside an active plant, operators must solve issues like high temperatures (up to more than 300degC inside a light-water reactor's primary piping), high wall thickness of components in the primary circuit and characteristic defect typologies. Magnetostrictive sensors are expected to overcome such issues due to their physical properties, namely robust constitution and simplicity. Recent experimental results have demonstrated magnetostrictive transducers can withstand temperatures close to 300degC. In this paper, new experimental tests conducted using such a methodology will be described and open issues related to high temperature guided wave applications (e.g. wave velocity or amplitude fluctuations during propagation in variable temperature components) will be discussed. (author)

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

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2008-01-01

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

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

Economics important in selecting monitoring techniques

International Nuclear Information System (INIS)

Moore, D.P.; Byars, H.G.

1990-01-01

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

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

International Nuclear Information System (INIS)

2011-01-01

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

Advanced ship systems condition monitoring for enhanced inspection, maintenance and decision making in ship operations

OpenAIRE

Lazakis, Iraklis; Dikis, Konstantinos; Michala, Anna Lito; Theotokatos, Gerasimos

2016-01-01

Structural and machinery failures in the day-to-day ship operations may lead to major accidents, endangering crew and\\ud passengers onboard, posing a threat to the environment, damaging the ship itself and having a great impact in terms of business\\ud losses. In this respect, this paper presents the INCASS (Inspection Capabilities for Enhanced Ship Safety) project which aims\\ud bringing an innovative solution to the ship inspection regime through the introduction of enhanced inspection of shi...

Risk-Informed Decisions Optimization in Inspection and Maintenance

International Nuclear Information System (INIS)

Robertas Alzbutas

2002-01-01

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)

A mobile robot for remote inspection of radioactive waste

International Nuclear Information System (INIS)

Suh, Y. C.; Kim, C. H.; Cho, J. W.; Choi, Y. S.; Kim, S. H.

2004-01-01

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

46 CFR 153.812 - Inspection for Certificate of Inspection.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Inspection for Certificate of Inspection. 153.812... CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS HAZARDOUS MATERIALS Design and Equipment Testing and Inspection § 153.812 Inspection for Certificate of Inspection. The rules governing the...

Storage monitoring systems for the year 2000

International Nuclear Information System (INIS)

Nilsen, C.; Pollock, R.

1997-01-01

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

Framework for Automated GD&T Inspection Using 3D Scanner

Science.gov (United States)

Pathak, Vimal Kumar; Singh, Amit Kumar; Sivadasan, M.; Singh, N. K.

2018-04-01

Geometric Dimensioning and Tolerancing (GD&T) is a typical dialect that helps designers, production faculty and quality monitors to convey design specifications in an effective and efficient manner. GD&T has been practiced since the start of machine component assembly but without overly naming it. However, in recent times industries have started increasingly emphasizing on it. One prominent area where most of the industries struggle with is quality inspection. Complete inspection process is mostly human intensive. Also, the use of conventional gauges and templates for inspection purpose highly depends on skill of workers and quality inspectors. In industries, the concept of 3D scanning is not new but is used only for creating 3D drawings or modelling of physical parts. However, the potential of 3D scanning as a powerful inspection tool is hardly explored. This study is centred on designing a procedure for automated inspection using 3D scanner. Linear, geometric and dimensional inspection of the most popular test bar-stepped bar, as a simple example was also carried out as per the new framework. The new generation engineering industries would definitely welcome this automated inspection procedure being quick and reliable with reduced human intervention.

Developments in mechanical ultrasonic inspection and qualification of NDE

International Nuclear Information System (INIS)

Kauppinen, P.; Pitkaenen, J.; Kuusinen, P.

2001-01-01

Reliability of non-destructive testing results has a direct influence on structural integrity assessment and safety of the inspected structures e.g. NPP primary circuit pressure boundaries. Advanced technology together with highly skilled and experienced personnel is required. One of the current trends is automation. Mechanised equipment can replace tedious manual work in positioning and moving of the transducers. Large areas can be scanned, analysed and numerically documented for direct comparison of eventual later repeated inspections. Another major trend is qualification, which aims to ensure that the inspection results are correct and fit the purpose. The suitability and proper operation of equipment, methods and personnel i.e. the whole chain shall be proven. This presentation summarises the advances in automation and qualification of non-destructive inspection during the second project year, Monitoring of material degradation was included in the studied topics and will also be shortly described. (author)

Acoustic Techniques for Structural Health Monitoring

Science.gov (United States)

Frankenstein, B.; Augustin, J.; Hentschel, D.; Schubert, F.; Köhler, B.; Meyendorf, N.

2008-02-01

Future safety and maintenance strategies for industrial components and vehicles are based on combinations of monitoring systems that are permanently attached to or embedded in the structure, and periodic inspections. The latter belongs to conventional nondestructive evaluation (NDE) and can be enhanced or partially replaced by structural health monitoring systems. However, the main benefit of this technology for the future will consist of systems that can be differently designed based on improved safety philosophies, including continuous monitoring. This approach will increase the efficiency of inspection procedures at reduced inspection times. The Fraunhofer IZFP Dresden Branch has developed network nodes, miniaturized transmitter and receiver systems for active and passive acoustical techniques and sensor systems that can be attached to or embedded into components or structures. These systems have been used to demonstrate intelligent sensor networks for the monitoring of aerospace structures, railway systems, wind energy generators, piping system and other components. Material discontinuities and flaws have been detected and monitored during full scale fatigue testing. This paper will discuss opportunities and future trends in nondestructive evaluation and health monitoring based on new sensor principles and advanced microelectronics. It will outline various application examples of monitoring systems based on acoustic techniques and will indicate further needs for research and development.

Inspection planning

International Nuclear Information System (INIS)

Korosec, D.; Levstek, M.F.

2001-01-01

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)

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

Review of In-Service Inspection and Repair Technique Developments for French Liquid Metal Fast Reactors

International Nuclear Information System (INIS)

Baque, F.

2005-01-01

In-service monitoring of nuclear plants is indispensable for both the Operator and the Regulator. The notion of in-service monitoring ranges from the continuous monitoring of the reactor in operation to the thorough in-service reactor inspection during programmed shutdowns. However, the highly specific environment found in French liquid metal fast reactor plants - Phenix and Superphenix - makes monitoring and inspection complicated because of the use of a sodium coolant that is hot, opaque, and difficult to drain.The Commissariat a l'Energie Atomique, in collaboration with its traditional French partners, Electricite de France utilities and FRAMATOME/Novatome Engineering, decided to conduct a 6-yr research and development program (1994-2000) to explore this problem vis-a-vis Superphenix, as well as the possibilities of intervening within the reactor block or on components in a sodium environment. Furthermore, the safety reevaluation of Phenix, conducted between 1994 and 2003, represented an excellent 'test bench' during which the limits of inspection processes - applied to an integrated reactor concept - were surpassed using techniques such as fuel subassembly head scanning, ultrasonic examination of the core support, and visual inspection of the cover-gas plenum following a partial sodium draining. Repair techniques were investigated for cleaning of sodium wet structure surfaces, cutting of damaged parts, and welding in sodium aerosol atmosphere. Both conventional and laser processes were tested

An intelligent inspection and survey robot. Volume 1

International Nuclear Information System (INIS)

1995-01-01

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

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.

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

International Nuclear Information System (INIS)

Joo, Young Sang; Lee, Jae Han

2007-02-01

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

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.

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.

Advanced inspection technology for non intrusive inspection (NII) program

International Nuclear Information System (INIS)

Zamir Mohamed Daud

2003-01-01

In the current economic environment, plants and facilities are under pressure to introduced cost saving as well as profit maximising measures. Among the many changes in the way things are run is a move towards Risk Based Inspection (RBI), with an emphasis on longer operating periods between shutdowns as well as to utilise components to their maximum capability. Underpinning and RBI program requires good data from an effective online inspections program, which would not require the shutdown of critical components. One methodology of online inspection is known as Non Intrusive Inspection (NII), an inspection philosophy with the objective of replacing internal inspection of a vessel by doing Non Destructive Testing (NDT) and inspections externally. To this end, a variety of advanced NDT techniques are needed to provide accurate online measurements. (Author)

Remote and unattended monitoring techniques

International Nuclear Information System (INIS)

Abedin-Zadeh, R.; Whichello, J.

1998-01-01

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

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

International Nuclear Information System (INIS)

Stepinski, Tadeusz; Olofsson, Tomas; Wennerstroem, Erik

2006-12-01

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

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.

Development of the radiation inspection system for food materials

Energy Technology Data Exchange (ETDEWEB)

Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of)

2015-10-15

Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement.

Development of the radiation inspection system for food materials

International Nuclear Information System (INIS)

Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang

2015-01-01

Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement

Overview of steam generator tube-inspection technology

International Nuclear Information System (INIS)

Obrutsky, L.; Renaud, J.; Lakhan, R.

2014-01-01

Degradation of steam generator (SG) tubing due to both mechanical and corrosion modes has resulted in extensive repairs and replacement of SGs around the world. The variety of degradation modes challenges the integrity of SG tubing and, therefore, the stations' reliability. Inspection and monitoring aimed at timely detection and characterization of the degradation is a key element for ensuring tube integrity. Up to the early-70's, the in-service inspection of SG tubing was carried out using single-frequency eddy current testing (ET) bobbin coils, which were adequate for the detection of volumetric degradation. By the mid-80's, additional modes of degradation such as pitting, intergranular attack, and axial and circumferential inside or outside diameter stress corrosion cracking had to be addressed. The need for timely, fast detection and characterization of these diverse modes of degradation motivated the development in the 90's of inspection systems based on advanced probe technology coupled with versatile instruments operated by fast computers and remote communication systems. SG inspection systems have progressed in the new millennium to a much higher level of automation, efficiency and reliability. Also, the role of Non Destructive Evaluation (NDE) has evolved from simple detection tools to diagnostic tools that provide input into integrity assessment decisions, fitness-far-service and operational assessments. This new role was motivated by tighter regulatory requirements to assure the safety of the public and the environment, better SG life management strategies and often self-imposed regulations. It led to the development of advanced probe technologies, more reliable and versatile instruments and robotics, better training and qualification of personnel and better data management and analysis systems. This paper provides a brief historical perspective regarding the evolution of SG inspections and analyzes the motivations behind that evolution. It presents an

Optimizing and joining future safeguards efforts by 'remote inspections'

International Nuclear Information System (INIS)

Zendel, M.; Khlebnikov, N.

2009-01-01

Full-text: Remote inspections have a large potential to save inspection effort in future routine safeguards implementation. Such inspections involve remote activities based on the analysis of data acquired in the field without the physical presence of an inspector, shifting the inspectors' priorities further toward unannounced inspections, complementary access activities and data evaluation. Large, automated and complex facilities require facility resident and specific safeguards equipment systems with features for unattended and remotely controlled operation as well as being integrated in the nuclear process. In many instances the use of such equipment jointly with the SSAC/RSAC and the operator is foreseen to achieve affordable effectiveness with a minimum level of intrusiveness to the facility operation. Where it becomes possible to achieve independent conclusions by this approach, the IAEA would make full use of the SSAC/RSAC, involving State inspectors and/or facility operators to operate inspection systems under remotely controlled IAEA mechanisms. These mechanisms would include documented procedures for routine joint-use, defining arrangements for data sharing, physical security and authentication mechanisms, recalibration and use of standards and software, maintenance, repair, storage and transportation. The level of cooperation and willingness of a State to implement such measures requested and properly justified by the IAEA will demonstrate its commitment to full transparency in its nuclear activities. Examples of existing remote inspection activities, including joint-use activities will be discussed. The future potential of remote inspections will be assessed considering technical developments and increased needs for process monitoring. Enhanced cooperation with SSAC/RSAC within the framework of remote inspections could further optimize the IAEA's inspection efforts while at the same time maintaining effective safeguards implementation. (author)

Improved plant availability by advanced condition based inspections

International Nuclear Information System (INIS)

Hulshof, Harry J.M.; Noteboom, Jan W.; Welberg, Paul G.M.; Bruijn, Leo E.

2004-01-01

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

Improved plant availability by advanced condition based inspections

Energy Technology Data Exchange (ETDEWEB)

Hulshof, Harry J.M.; Noteboom, Jan W; Welberg, Paul G.M.; Bruijn, Leo E

2004-06-01

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.

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)

Senoo, Makoto; Yoshida, Tomiharu; Omote, Tatsuyuki; Tanaka, Keiji; Koga, Kazunori

1996-01-01

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)

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

International Nuclear Information System (INIS)

Kumakura, Shinichi; Gotoh, Yoshiki; Kikuchi, Masahiro

2011-01-01

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)

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

International Nuclear Information System (INIS)

Fresco, A.; Subudhi, M.

1992-01-01

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

Post-Closure Inspection Report for Corrective Action Unit 453: Area 9 UXO Landfill Tonopah Test Range, Nevada, Calendar Year 2000; TOPICAL

International Nuclear Information System (INIS)

K. B. Campbell

2001-01-01

Post-closure monitoring requirements for the Area 9 Unexploded Ordnance 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. 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. Post-closure monitoring at CAU 453 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 20, 2000 and November 21, 2000. Both site inspections were conducted after NDEP approval of the CR, and 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

Report of Radioisotope Inspection Technical Committee

International Nuclear Information System (INIS)

Otani, H.

1980-01-01

For the purpose of unifying the method of performance test for the routine management of the performance of RI equipments, the check-up of performance at the time of purchasing the equipments or research works, the Committee has continued the investigation on the method of performance test on RI equipments. Now, the definite plans have been decided regarding the method of performance test on radioisotope monitoring instruments and the measuring instruments for RI samples, therefore they are reported hereinafter. As for the radioisotope monitoring instruments, Curie meter, area monitor, water monitor, gas monitor and hand, foot and cloth monitor were taken up, and the items of inspection, the purposes, the testing methods, the expression of measured results and their evaluation were discussed. The accuracy of measurement of absolute radio-activity is important in Curie meter, the stability of continuous monitoring is important in general monitors, and the limit of measurement is important in the hand, foot and cloth monitor. As for the measuring instruments for radioactive materials, the efficiency of counting, linearity and stability were taken up as the items of performance test, and other matters to which attention should be paid were added. These were described, dividing into well type scintillation counter and liquid scintillation counter. (Kako, I.)

Pathology Residents Comprise Inspection Team for a CAP Self-Inspection

Directory of Open Access Journals (Sweden)

Stacy G. Beal MD

2017-03-01

Full Text Available We report our experience at the University of Florida in which residents and fellows served as the inspection team for a College of American Pathologists (CAP self-inspection. We aimed to determine whether the CAP self-inspection could serve as a learning opportunity for pathology residents and fellows. To prepare for the inspection, we provided a series of 4 lunchtime seminars covering numerous laboratory management topics relating to inspections and laboratory quality. Preparation for the inspection began approximately 4 months prior to the date of the inspection. The intent was to simulate a CAP peer inspection, with the exception that the date was announced. The associate residency program director served as the team leader. All residents and fellows completed inspector training provided by CAP, and the team leader completed the team leader training. A 20 question pre- and posttest was administered; additionally, an anonymous survey was given after the inspection. The residents’ and fellows’ posttest scores were an average of 15% higher than on the pretest ( P < .01. The surveys as well as subjective comments were overwhelmingly positive. In conclusion, the resident’s and fellow’s experience as an inspector during a CAP self-inspection was a useful tool to learn accreditation and laboratory management.

Primary School Inspection: A Supporting Service for Education.

Science.gov (United States)

Lyons, Raymond F.; Pritchard, Mervyn W.

The first section of this summary report is directed to an examination of the nature of the functions of inspection in the six countries examined--Algeria, Nigeria, Pakistan, Peru, Venezuela, and Zambia--and consideration of the content of effective monitoring of and advising on the work of teachers and schools. Conditions that make it possible…

Ultrasonic inspection

International Nuclear Information System (INIS)

Satittada, Gannaga

1984-01-01

Ultrasonic inspection is one of the most widely used methods for nondestructive inspection. The beam of high-frequency sound wave, ultrasonic wave, is introduced into the material. It travels through the material with some attendant loss of energy and can be reflected at interfaces. The reflected beam is detected and analyzed. Ultrasonic inspection is used to detect flaws in metal parts as well as in welded, brazed and bonded joints during research work and developing production and service. It is also used to detect and locate porosity, pipe, and flakes. In addition, it can be used for the measurement of metal thickness. Ultrasonic inspection is therefore used for quality control and material inspection in all major industries

SmartInspect: Smart Contract Inspection Technical Report

OpenAIRE

Bragagnolo , Santiago; Rocha , Henrique ,; Denker , Marcus; Ducasse , Stéphane

2017-01-01

Smart contracts are embedded procedures stored with the data they act upon. Debugging deployed Smart Contracts is a difficult task since once deployed, the code cannot be reexecuted and inspecting a simple attribute is not easily possible because data is encoded. In this technical report, we present SmartInspect to address the lack of inspectability of a deployed contract. Our solution analyses the contract state by using decompilation techniques and a mirror-based architecture to represent t...

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

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

International Nuclear Information System (INIS)

2012-01-01

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.

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.

Inspection of the UO2 special fuel for the prototype heavy water reactor 'FUGEN'

International Nuclear Information System (INIS)

Miura, Makoto; Ohmori, Takuro; Yoshino, Hiroyuki; Matsui, Hiromasa; Hirosawa, Naonori

1979-01-01

UO 2 special fuel assemblies are the fuel for material irradiation incorporating irradiation specimens, for the prototype heavy water reactor ''FUGEN''. In order to monitor the behavior of the pressure tube material irradiated with neutrons for long time, monitoring specimens were equipped in the core. This special fuel was fabricated by the Nuclear Fuel Industries, Ltd. (NFI), and the fuel cladding tubes, the capsule guide tubes and the capsule tubes were furnished by PNC. The irradiation specimens were prepared by PNC, and incorporated into the assemblies by NFI. The inspection by PNC on the special fuel assemblies was conducted following the inspection by the maker, which was made on UO 2 pellets, fuel element and assembly parts except cladding tubes, after completing the fabrication. The specifications of the special fuel, especially for the outer and inner layer pellets, the outer and inner layer fuel elements and the fuel assemblies, are presented. The flow sheet for the inspection process and surveillance test of special fuel assemblies is illustrated. The inspection items, the materials and the quantity inspection are tabulated for the fuel elements, the fuel assemblies and the irradiation capsules, respectively. The structure of a special type fuel assembly is shown. For each inspection, the inspection methods and items and the results are explained. As for the results of inspection of the special fuel, the UO 2 pellets, fuel element parts, fuel elements, fuel assembly parts, fuel assemblies, capsules and irradiation specimens were in accordance with the specifications. Regarding the situation of the quality control in the processes, check was made with many documents, and it was recognized that the quality control was performed in the quality assurance program. (Nakai, Y.)

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2011

International Nuclear Information System (INIS)

2010-07-01

The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland, 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 inspection follow up and review. The report also provides an overview of the main features of the quality system

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2013

International Nuclear Information System (INIS)

2013-04-01

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

Inspection vehicle

International Nuclear Information System (INIS)

Takahashi, Masaki; Omote, Tatsuyuki; Yoneya, Yutaka; Tanaka, Keiji; Waki, Tetsuro; Yoshida, Tomiji; Kido, Tsuyoshi.

1993-01-01

An inspection vehicle comprises a small-sized battery directly connected with a power motor or a direct power source from trolly lines and a switching circuit operated by external signals. The switch judges advance or retreat by two kinds of signals and the inspection vehicle is recovered by self-running. In order to recover the abnormally stopped inspection vehicle to the targeted place, the inspection vehicle is made in a free-running state by using a clutch mechanism and is pushed by an other vehicle. (T.M.)

Pre-service inspection and in-service inspection in Japan

International Nuclear Information System (INIS)

Uebayashi, T.; Miyake, Y.

1985-01-01

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

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)

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

Overview of steam generator tube-inspection technology

Energy Technology Data Exchange (ETDEWEB)

Obrutsky, L.; Renaud, J.; Lakhan, R., E-mail: obrutskl@aecl.ca, E-mail: renaudj@aecl.ca, E-mail: lakhanr@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2014-03-15

Degradation of steam generator (SG) tubing due to both mechanical and corrosion modes has resulted in extensive repairs and replacement of SGs around the world. The variety of degradation modes challenges the integrity of SG tubing and, therefore, the stations' reliability. Inspection and monitoring aimed at timely detection and characterization of the degradation is a key element for ensuring tube integrity. Up to the early-70's, the in-service inspection of SG tubing was carried out using single-frequency eddy current testing (ET) bobbin coils, which were adequate for the detection of volumetric degradation. By the mid-80's, additional modes of degradation such as pitting, intergranular attack, and axial and circumferential inside or outside diameter stress corrosion cracking had to be addressed. The need for timely, fast detection and characterization of these diverse modes of degradation motivated the development in the 90's of inspection systems based on advanced probe technology coupled with versatile instruments operated by fast computers and remote communication systems. SG inspection systems have progressed in the new millennium to a much higher level of automation, efficiency and reliability. Also, the role of Non Destructive Evaluation (NDE) has evolved from simple detection tools to diagnostic tools that provide input into integrity assessment decisions, fitness-far-service and operational assessments. This new role was motivated by tighter regulatory requirements to assure the safety of the public and the environment, better SG life management strategies and often self-imposed regulations. It led to the development of advanced probe technologies, more reliable and versatile instruments and robotics, better training and qualification of personnel and better data management and analysis systems. This paper provides a brief historical perspective regarding the evolution of SG inspections and analyzes the motivations behind that

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.

Study on Classification Accuracy Inspection of Land Cover Data Aided by Automatic Image Change Detection Technology

Science.gov (United States)

Xie, W.-J.; Zhang, L.; Chen, H.-P.; Zhou, J.; Mao, W.-J.

2018-04-01

The purpose of carrying out national geographic conditions monitoring is to obtain information of surface changes caused by human social and economic activities, so that the geographic information can be used to offer better services for the government, enterprise and public. Land cover data contains detailed geographic conditions information, thus has been listed as one of the important achievements in the national geographic conditions monitoring project. At present, the main issue of the production of the land cover data is about how to improve the classification accuracy. For the land cover data quality inspection and acceptance, classification accuracy is also an important check point. So far, the classification accuracy inspection is mainly based on human-computer interaction or manual inspection in the project, which are time consuming and laborious. By harnessing the automatic high-resolution remote sensing image change detection technology based on the ERDAS IMAGINE platform, this paper carried out the classification accuracy inspection test of land cover data in the project, and presented a corresponding technical route, which includes data pre-processing, change detection, result output and information extraction. The result of the quality inspection test shows the effectiveness of the technical route, which can meet the inspection needs for the two typical errors, that is, missing and incorrect update error, and effectively reduces the work intensity of human-computer interaction inspection for quality inspectors, and also provides a technical reference for the data production and quality control of the land cover data.

Life sciences laboratory breadboard simulations for shuttle

Science.gov (United States)

Taketa, S. T.; Simmonds, R. C.; Callahan, P. X.

1975-01-01

Breadboard simulations of life sciences laboratory concepts for conducting bioresearch in space were undertaken as part of the concept verification testing program. Breadboard simulations were conducted to test concepts of and scope problems associated with bioresearch support equipment and facility requirements and their operational integration for conducting manned research in earth orbital missions. It emphasized requirements, functions, and procedures for candidate research on crew members (simulated) and subhuman primates and on typical radioisotope studies in rats, a rooster, and plants.

Super Phenix 1: in Service inspection of main and safety tanks weldments

International Nuclear Information System (INIS)

Asty, Michel; Vertut, Jean; Argous, J.P.

1980-05-01

In service inspection of the main tank of the Super Phenix 1 reactor is a new demand as compared to Phenix: the authorities have asked that surface and internal defects could 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

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

Energy Technology Data Exchange (ETDEWEB)

Asty, M [DTech/STA, Centre d' Etudes Nucleaires de Saclay (France); Vertut, J [DPR/STEP, Centre d' Etudes Nucleaires de Saclay (France); Argous, J P [DRNR/STRS, Centre d' Etudes Nucleaires de Cadarache (France)

1980-11-01

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)

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

International Nuclear Information System (INIS)

Asty, M.; Vertut, J.; Argous, J.P.

1980-01-01

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)

Advanced management of pipe wall thinning based on prediction-monitor fusion

International Nuclear Information System (INIS)

Kojima, Fumio; Uchida, Shunsuke

2012-01-01

This article is concerned with pipe wall thinning management system by means of hybrid use of simulation and monitoring. First, the computer-aided simulation for predicting wear rate of piping system is developed based on elucidation of thinning mechanism such as flow-accelerated corrosion (FAC). The accurate prediction of wear rate allows us the useful information on region of interest of inspection. Secondly, several monitoring methods are considered in accordance with interest of inspection. Thirdly, probability of detection (POD) is considered for the reliability of inspection data. The final part of this article is devoted to how to improve safety performance under the hybrid use of predicting and monitoring on the proposed pipe wall management. (author)

APPLYING SIMPLE TECHNOLOGY ACCOMPLISHES VISUAL INSPECTION CHALLENGES

International Nuclear Information System (INIS)

Robinson, C

2007-01-01

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

Bio-Research: Submissions

African Journals Online (AJOL)

In: Proceedings of the 20th Convention of The Institute of Brewing (Australia and New ... The publishers reserve the right to reduce or enlarge line drawings. ... are requested to pay $ 50 (US dollars) to the Editor-in-Chief in certified bank draft.

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.

Personnel Monitoring Department - DEMIN

International Nuclear Information System (INIS)

1989-01-01

The activities and purposes of the Personnel Monitoring Dept. of the Institute of Radioprotection and Dosimetry of the Brazilian CNEN are presented. A summary of the personnel monitoring service is given, such as dosemeters supply, laboratorial inspections, and so on. The programs of working, publishing, courses and personnel interchange are also presented. (J.A.M.M.)

Inspection activities of other strategic points (OSPs) at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Kaifuki, Yukinobu; Ebata, Takashi; Nakano, Sadayuki; Fujimaki, Kazunori

2008-01-01

At Rokkasho Reprocessing Plant (RRP), Active Test (AT) using actual spent fuels for the final confirmation of the equipment and the system has been performed since March 31, 2006 toward the commercial operation. The safeguards inspection during AT is required in the same manner as commercial operation condition because plutonium is handled. In RRP automated verification systems are established by using unattended verification systems including a number of process monitoring systems along with main plutonium handling process from the spent fuel storage until the MOX product storages. Even under the modernized safeguards, inspection activities at Other Strategic Points (OSPs) are required to confirm plant status in accordance with requirements of the IAEA safeguards criteria. This paper presents procedures and inspection activities at OSPs which has been implemented in RRP since start of AT. (author)

40 CFR 63.1510 - Monitoring requirements.

Science.gov (United States)

2010-07-01

... Analysis Division; Emission Measurement Center (MD-19), Research Triangle Park, NC 27711. This document... inspector training program; (3) An established correlation between visual inspection and physical... operating parameters to be monitored, the monitoring approach and technique, and how the limit is to be...

Shell Inspection History and Current CMM Inspection Efforts

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-01-26

The following report provides a review of past and current CMM Shell Inspection efforts. Calibration of the Sheffield rotary contour gauge has expired and the primary inspector, Matthew Naranjo, has retired. Efforts within the Inspection team are transitioning from maintaining and training new inspectors on Sheffield to off-the-shelf CMM technology. Although inspection of a shell has many requirements, the scope of the data presented in this report focuses on the inner contour, outer contour, radial wall thickness and mass comparisons.

Randomization of inspections

International Nuclear Information System (INIS)

Markin, J.T.

1989-01-01

As the numbers and complexity of nuclear facilities increase, limitations on resources for international safeguards may restrict attainment of safeguards goals. One option for improving the efficiency of limited resources is to expand the current inspection regime to include random allocation of the amount and frequency of inspection effort to material strata or to facilities. This paper identifies the changes in safeguards policy, administrative procedures, and operational procedures that would be necessary to accommodate randomized inspections and identifies those situations where randomization can improve inspection efficiency and those situations where the current nonrandom inspections should be maintained. 9 refs., 1 tab

POST CLOSURE INSPECTION AND MONITORING REPORT FOR CORRECTIVE ACTION UNIT 417: CENTRAL NEVADA TEST AREA - SURFACE, HOT CREEK VALLEY, NEVADA; FOR CALENDAR YEAR 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-01

bentonite during the first quarter of 2006 and monitored during subsequent inspections. The cover vegetation was healthy and well established. 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 inspections at UC-3 indicated that the sites are in excellent condition. All monuments and signs showed no displacement, damage, or removal. A small erosion gully from spring rain runoff was observed during the June inspection, but it did not grow to an actionable level during 2005. No other issues or concerns were identified. Inspections performed at UC-4 Mud Pit C cover revealed that erosion rills were formed during March and September exposing the geosynthetic clay liner. Both erosion rills were repaired within 90 days of reporting. Sparse vegetation is present on the cover. The overall condition of the monuments, fence, and gate are in good condition. No issues were identified with the warning signs and monuments at the other four UC-4 locations. Subsidence surveys were conducted at UC-1 CMP and UC-4 Mud Pit C in March and September of 2005. The results of the subsidence surveys indicate that the covers are performing as expected, and no unusual subsidence was observed. The June vegetation survey of the UC-1 CMP cover and adjacent areas indicated that the revegetation has been very successful. The vegetation should continue to be monitored to document any changes in the plant community and identify conditions that could potentially require remedial action in order to maintain a viable vegetative cover on the site. Vegetation surveys should be conducted only as required. Precipitation during 2005 was above average, with an annual rainfall total of 21.79 centimeters (8.58 inches). Soil moisture content data show that the UC-1 CMP cover is performing as designed, with evapotranspiration effectively removing water from the cover. It is recommended to continue

Visual inspection technology of the narrow and small confined area for monitoring feederpipe support of pressure tube in calandria reactor

Energy Technology Data Exchange (ETDEWEB)

Cho, Jae Wan; Lee, Nam Ho; Choi, Young Soo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-12-01

There are 760 feederpipes, which they are connected to inlet/outlet of the 380 pressure tube channels on the front of the calandria, in CANDU-type Reactor of Wolsung Nuclear Power Plant. As an ISI(In-Service Inspection) and PSI (Post-Service Inspection) requirements, maintenance activities of measuring the thickness of curvilinear part of feederpipe and inspecting the feederpipe support area within calandria are needed to ensure continued reliable operation of nuclear power plant. And ultrasonic probe is used to measure the thickness of curvilinear part of feederpipe, however workers are exposed to radioactivity irradiation during the measurement period. But, it is exposed to radioactivity irradiation during the measurement period. But, it is impossible to inspect feederpipe support area thoroughly because of narrow and confined accessibility, that is , an inspection space between the pressure tube channels is less than 100 mm and pipes in feederpipe support area are congested. And also, workers involved in inspecting feederpipe support area are under the jeopardy of high-level radiation exposure. Concerns about sliding home, which make the move of feederpipe connected to pressure tube channel smooth as pressure tube expands and contracts in its axial direction, stuck to feedeerpipe support and some of the structural components have made necessary the development of video inspection probe system with narrow and confined accessibility to observe and inspect feederpipe support area more close. Using video inspection probe system, it is possible to inspect and repair abnormality of feederpipe support connected to pressure tube channels of the calandria more accurate and quantative than naked eye. Therefore, that will do much for ensuring safety of CANDU-type nuclear power plant. 45 figs.,31 tabs. (Author)

Simulating the service life performance of an inspected group of jacket-type structures

DEFF Research Database (Denmark)

Schneider, Ronald; Thöns, Sebastian; Rogge, Andreas

2017-01-01

and risk. We intend to adopt this approach to optimize inspection, monitoring and repair activities for offshore wind park support structures. As a first step, we simulate – in analogy to an offshore wind park – the service life performance of an inspected group of jacket-type frames. The performance......A novel method for risk-based optimization of inspection and repair strategies for deteriorating structural systems has recently been proposed. The method defines heuristics at the system level to reduce the number of possible strategies. For each defined strategy, it computes the updated system...... failure probability conditional on simulated inspection and repair histories, and evaluates the associated costs and risk. The expected total service life costs and risk for a strategy are finally determined using Monte Carlo simulation. The optimal strategy minimizes the expected total service life costs...

Inspection of internal tank welds using the ACFM inspection method

International Nuclear Information System (INIS)

Topp, D.A.; Lugg, M.C.

2009-01-01

The paper describes recent developments of the ACFM technique and describes several case studies where ACFM has been used to inspect the internal plate welds on large steel storage tanks in refineries. For weld inspection, conventional methods such as magnetic particle inspection or vacuum box testing are generally used. This paper presents comparisons of the results from ACFM with those from the conventional methods, from which conclusions are drawn as to the benefits this technique offers in terms of cost, time savings and inspection reliability. (author)

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.

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2012

International Nuclear Information System (INIS)

2012-04-01

The purpose of this document is to promote transparency in the activities of the RPII. It explains aspects of the internal workings of the Regulation and Information Management Division of the Institute to aid understanding of the processes and decisions of that Division which may impact on licensees and other interested parties. The objective of the report is to provide an overview of inspection activities of the 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

Technology of remote monitoring for nuclear activity monitoring

International Nuclear Information System (INIS)

Kwack, Ehn Ho; Kim, Jong Soo; Yoon, Wan Ki; Park, Sung Sik; Na, Won Woo; An, Jin Soo; Cha, Hong Ryul; Kim, Jung Soo

2000-05-01

In a view of safeguards monitoring at nuclear facilities, the monitoring is changing to remote method so that this report is described to remote monitoring(RM) applying on commercial NPP in Korea. To enhance IAEA safeguards efficiency and effectiveness, IAEA is taking into account of remote monitoring system(RMS) and testing as a field trial. IRMP(International Remote Monitoring Project) in participating many nations for development of RMS is proceeding their project such as technical exchange and research etc. In case of our country are carrying out the research relevant RM since acceptance RMS at 7th ROK-IAEA safeguards implementation review meeting. With a view to enhancement the RMS, installation location and element technology of the RM equipment are evaluated in a view of safeguards in Korea LWRs, and proposed a procedure for national inspection application through remote data evaluation from Younggwang-3 NPP. These results are large valuable to use of national inspection at time point extending installation to all Korea PWR NPP. In case of CANDU, neutron, gamma measurement and basic concept of network using optical fiber scintillating detector as remote verification method for dry storage canister are described. Also RM basic design of spent fuel transfer campaign is described that unattended RM without inspector instead of performing in participating together with IAEA and national inspector. The transfer campaign means the spent fuel storage pond to dry storage canister for about two months every year. Therefore, positively participation of IAEA strength safeguards project will be increased transparency for our nuclear activity as well as contributed to national relevant industry

Technology of remote monitoring for nuclear activity monitoring

Energy Technology Data Exchange (ETDEWEB)

Kwack, Ehn Ho; Kim, Jong Soo; Yoon, Wan Ki; Park, Sung Sik; Na, Won Woo; An, Jin Soo; Cha, Hong Ryul; Kim, Jung Soo

2000-05-01

In a view of safeguards monitoring at nuclear facilities, the monitoring is changing to remote method so that this report is described to remote monitoring(RM) applying on commercial NPP in Korea. To enhance IAEA safeguards efficiency and effectiveness, IAEA is taking into account of remote monitoring system(RMS) and testing as a field trial. IRMP(International Remote Monitoring Project) in participating many nations for development of RMS is proceeding their project such as technical exchange and research etc. In case of our country are carrying out the research relevant RM since acceptance RMS at 7th ROK-IAEA safeguards implementation review meeting. With a view to enhancement the RMS, installation location and element technology of the RM equipment are evaluated in a view of safeguards in Korea LWRs, and proposed a procedure for national inspection application through remote data evaluation from Younggwang-3 NPP. These results are large valuable to use of national inspection at time point extending installation to all Korea PWR NPP. In case of CANDU, neutron, gamma measurement and basic concept of network using optical fiber scintillating detector as remote verification method for dry storage canister are described. Also RM basic design of spent fuel transfer campaign is described that unattended RM without inspector instead of performing in participating together with IAEA and national inspector. The transfer campaign means the spent fuel storage pond to dry storage canister for about two months every year. Therefore, positively participation of IAEA strength safeguards project will be increased transparency for our nuclear activity as well as contributed to national relevant industry.

Technology Assessment of the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Woodley, Anthony

1998-01-01

...) Challenge Inspections. The CWC is an intrusive inspection. The Challenge Inspection allows for a team of international inspectors to inspect on very short notice a naval facility suspected of violating the CWC...

Process Improvement to the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Triplett, William

1997-01-01

...) Challenge Inspection. The CWC is an intensive inspection. The Challenge Inspection allows for a team of international inspectors to inspect a naval facility suspected of violating the CWC on very short notice...

Research on the inspection robot for cable tunnel

Science.gov (United States)

Xin, Shihao

2017-03-01

Robot by mechanical obstacle, double end communication, remote control and monitoring software components. The mechanical obstacle part mainly uses the tracked mobile robot mechanism, in order to facilitate the design and installation of the robot, the other auxiliary swing arm; double side communication part used a combination of communication wire communication with wireless communication, great improve the communication range of the robot. When the robot is controlled by far detection range, using wired communication control, on the other hand, using wireless communication; remote control part mainly completes the inspection robot walking, navigation, positioning and identification of cloud platform control. In order to improve the reliability of its operation, the preliminary selection of IPC as the control core the movable body selection program hierarchical structure as a design basis; monitoring software part is the core part of the robot, which has a definite diagnosis Can be instead of manual simple fault judgment, instead the robot as a remote actuators, staff as long as the remote control can be, do not have to body at the scene. Four parts are independent of each other but are related to each other, the realization of the structure of independence and coherence, easy maintenance and coordination work. Robot with real-time positioning function and remote control function, greatly improves the IT operation. Robot remote monitor, to avoid the direct contact with the staff and line, thereby reducing the accident casualties, for the safety of the inspection work has far-reaching significance.

General inspection strategy for fault diagnosis-minimizing the inspection costs

International Nuclear Information System (INIS)

Reinertsen, Rune; Wang Xiaozhong

1995-01-01

In this paper, a general inspection strategy for system fault diagnosis is presented. The procedure presented in this paper, is an improvement of methods described in papers by , and . This general strategy provides the optimal inspection procedure when the inspections require unequal effort and the minimum cut set probabilities are unequal. This feature makes the procedure described in this paper more useful for practical applications than the most recent procedure presented in the paper by Najmus-Saqib and Ishaque, which requires the minimum cut set probabilities to be equal. The inspection strategy described in this paper is based on first inspecting the basic event that will provide the maximum information gain per unit cost invested. The information gain is measured by the decrease of Shannon entropy. A detailed tutorial example is presented

Cargo container inspection test program at ARPA's Nonintrusive Inspection Technology Testbed

Science.gov (United States)

Volberding, Roy W.; Khan, Siraj M.

1994-10-01

An x-ray-based cargo inspection system test program is being conducted at the Advanced Research Project Agency (ARPA)-sponsored Nonintrusive Inspection Technology Testbed (NITT) located in the Port of Tacoma, Washington. The test program seeks to determine the performance that can be expected from a dual, high-energy x-ray cargo inspection system when inspecting ISO cargo containers. This paper describes an intensive, three-month, system test involving two independent test groups, one representing the criminal smuggling element and the other representing the law enforcement community. The first group, the `Red Team', prepares ISO containers for inspection at an off-site facility. An algorithm randomly selects and indicates the positions and preparation of cargoes within a container. The prepared container is dispatched to the NITT for inspection by the `Blue Team'. After in-gate processing, it is queued for examination. The Blue Team inspects the container and decides whether or not to pass the container. The shipment undergoes out-gate processing and returns to the Red Team. The results of the inspection are recorded for subsequent analysis. The test process, including its governing protocol, the cargoes, container preparation, the examination and results available at the time of submission are presented.

Development of inspection safety evaluation technology

Energy Technology Data Exchange (ETDEWEB)

Yoon, Seok Chul; Yoon, Yeo Chang; Kim, Jong Soo; Lee, Tae Young; Kim, Chang Ryol; Lee, Hyung Sub; Kim, Jong Soo

1995-12-01

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.

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 not...

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. Final report

International Nuclear Information System (INIS)

Kizer, J.A.

1981-10-01

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

Condition Assessment of the Timber Structures of a Century-Old Industrial Building Using a Nondestructive Inspection Procedure

Science.gov (United States)

Xiping Wang; Marko Teder; James Wacker

2013-01-01

This paper reports an in situ inspection project conducted on heavy timber structures of a century-old industrial building at a paper manufacturing facility. A nondestructive inspection procedure was employed to evaluate the true condition of the heavy timbers that serve as the main framing structure of the building. The on-site investigation involved monitoring of the...

Post-Closure Inspection Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench Tonopah Test Range, Nevada, Calendar Year 2000

Energy Technology Data Exchange (ETDEWEB)

K. B. Campbell

2001-06-01

Post-closure monitoring requirements for the Roller Coaster Sewage Lagoons and North Disposal Trench (Corrective Action Unit [CAW 404]) (Figure 1) are described in Closure Report for Corrective Action Unit 404, Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, report number DOE/NV--187. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on September 11, 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 18, 1999. Post-closure monitoring at CAU 404 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. The site inspections were conducted after completion of the revegetation activities (October 30, 1997) and NDEP approval of the CR (May 18, 1999). All site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of 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.

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

International Nuclear Information System (INIS)

Abdel-Ghani, A.H.

2000-01-01

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

CTBT on-site inspections

Science.gov (United States)

Zucca, J. J.

2014-05-01

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.

Identification of areas and time intervals for inservice inspections; Auswahl der Pruefbereiche und -intervalle fuer wiederkehrende Pruefungen

Energy Technology Data Exchange (ETDEWEB)

Metzner, K J [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Herter, K H [Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt; Schoeckle, F [Amtec Messtechnischer Service, Lauffen (Germany)

1998-11-01

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) [Deutsch] Wiederkehrende Pruefungen sind ein wichtiger redundanter Teil der Gesamtmassnahmen zur Gewaehrleistung der Komponentenintegritaet waehrend des Betriebes von Kernkraftwerken. Ihre Wirksamkeit muss jedoch in enger Verbindung mit den die Komponentenqualitaet erzeugenden Massnahmen (Auslegung und Herstellung) und den die Komponentenqualitaet erhaltenden Ueberwachungmassnahmen waehrend des Betriebes gesehen werden. Wenn die vorhandene Betriebsueberwachung eine umfassende Kenntnis der bisherigen Betriebsbelastungen ermoeglicht (Ueberwachung der Ursachen

78 FR 54861 - Inspection, Repair, and Maintenance; Driver-Vehicle Inspection Report

Science.gov (United States)

2013-09-06

... No. FMCSA-2012-0336] RIN 2126-AB46 Inspection, Repair, and Maintenance; Driver-Vehicle Inspection... Federal Register of August 7, 2013, regarding driver vehicle inspection reports. The corrections involve..., Vehicle and Roadside Operations Division, Office of Bus and Truck Standards and Operations, Federal Motor...

Additive Manufacturing Infrared Inspection

Science.gov (United States)

Gaddy, Darrell; Nettles, Mindy

2015-01-01

The Additive Manufacturing Infrared Inspection Task started the development of a real-time dimensional inspection technique and digital quality record for the additive manufacturing process using infrared camera imaging and processing techniques. This project will benefit additive manufacturing by providing real-time inspection of internal geometry that is not currently possible and reduce the time and cost of additive manufactured parts with automated real-time dimensional inspections which deletes post-production inspections.

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

INSPECT: a package of computer programs for planning safeguards inspections

International Nuclear Information System (INIS)

Wincek, M.A.; Mullen, M.F.

1979-04-01

As part of the U.S. program to provide technical assistance to the International Atomic Energy Agency, a package of computer programs was developed for use in planning safeguards inspections of various types of nuclear facilities. The INSPECT software package is a set of five interactive FORTRAN programs which can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, a measure of the effectiveness of the inspection, and a measurement of the cost of implementing the inspection plan. This report describes the programs and explains how to use them

Post-Closure Inspection Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench Tonopah Test Range, Nevada, Calendar Year 2000; TOPICAL

International Nuclear Information System (INIS)

K. B. Campbell

2001-01-01

Post-closure monitoring requirements for the Roller Coaster Sewage Lagoons and North Disposal Trench (Corrective Action Unit[CAW 404]) (Figure 1) are described in Closure Report for Corrective Action Unit 404, Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, report number DOE/NV-187. The Closure Report (CR) was submitted to the Nevada Division of Environmental Protection (NDEP) on September 11, 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 18, 1999. Post-closure monitoring at CAU 404 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. The site inspections were conducted after completion of the revegetation activities (October 30, 1997) and NDEP approval of the CR (May 18, 1999). All site inspections were conducted in accordance with the Post-Closure Monitoring Plan in the NDEP-approved CR. This report includes copies of 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

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

Inspection of dissimilar metal welds in reactor pressure vessels in Spain

International Nuclear Information System (INIS)

Gadea, J.R.; Regidor, J.J.; Pelaez, J.A.; Serrano, P.

2011-01-01

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 critical

Health Monitoring of Composite Material Structures using a Vibrometry Technique

Science.gov (United States)

Schulz, Mark J.

1997-01-01

Large composite material structures such as aircraft and Reusable Launch Vehicles (RLVS) operate in severe environments comprised of vehicle dynamic loads, aerodynamic loads, engine vibration, foreign object impact, lightning strikes, corrosion, and moisture absorption. These structures are susceptible to damage such as delamination, fiber breaking/pullout, matrix cracking, and hygrothermal strain. To ensure human safety and load-bearing integrity, these structures must be inspected to detect and locate often invisible damage and faults before becoming catastrophic. Moreover, nearly all future structures will need some type of in-service inspection technique to increase their useful life and reduce maintenance and overall costs. Possible techniques for monitoring the health and indicating damage on composite structures include: c-scan, thermography, acoustic emissions using piezoceramic actuators or fiber-optic wires with gratings, laser ultrasound, shearography, holography, x-ray, and others. These techniques have limitations in detecting damage that is beneath the surface of the structure, far away from a sensor location, or during operation of the vehicle. The objective of this project is to develop a more global method for damage detection that is based on structural dynamics principles, and can inspect for damage when the structure is subjected to vibratory loads to expose faults that may not be evident by static inspection. A Transmittance Function Monitoring (TFM) method is being developed in this project for ground-based inspection and operational health monitoring of large composite structures as a RLV. A comparison of the features of existing health monitoring approaches and the proposed TFM method is given.

Methods of In-Process On-Machine Auto-Inspection of Dimensional Error and Auto-Compensation of Tool Wear for Precision Turning

Directory of Open Access Journals (Sweden)

Shih-Ming Wang

2016-04-01

Full Text Available The purpose of this study is mainly to develop an information and communication technology (ICT-based intelligent dimension inspection and tool wear compensation method for precision tuning. With the use of vibration signal processing/characteristics analysis technology combined with ICT, statistical analysis, and diagnosis algorithms, the method can be used to proceed with an on-line dimension inspection and on-machine tool wear auto-compensation for the turning process. Meanwhile, the method can also monitor critical tool life to identify the appropriate time for cutter replacement to reduce machining costs and improve the production efficiency of the turning process. Compared to the traditional ways, the method offers the advantages of requiring less manpower, and having better production efficiency, high tool life, fewer scrap parts, and low costs for inspection instruments. Algorithms and diagnosis threshold values for the detection, cutter wear compensation, and cutter life monitoring were developed. In addition, a bilateral communication module utilizing FANUC Open CNC (computer numerical control Application Programming Interface (API Spec was developed for the on-line extraction of instant NC (numerical control codes for monitoring and transmit commands to CNC controllers for cutter wear compensation. With use of local area networks (LAN to deliver the detection and correction information, the proposed method was able to remotely control the on-machine monitoring process and upload the machining and inspection data to a remote central platform for further production optimization. The verification experiments were conducted on a turning production line. The results showed that the system provided 93% correction for size inspection and 100% correction for cutter wear compensation.

Belief–logic conflict resolution in syllogistic reasoning: Inspection-time evidence for a parallel process model

OpenAIRE

Stupple, Edward J.N; Ball, Linden

2008-01-01

An experiment is reported examining dual-process models of belief bias in syllogistic reasoning using a problem complexity manipulation and an inspection-time method to monitor processing latencies for premises and conclusions. Endorsement rates indicated increased belief bias on complex problems, a finding that runs counter to the “belief-first” selective scrutiny model, but which is consistent with other theories, including “reasoning-first” and “parallel-process” models. Inspection-time da...

Advanced ultrasonic inspections

International Nuclear Information System (INIS)

Ghia, S.

1990-08-01

Acoustic Emission (AE) continuous monitoring and periodical inspections by advanced ultrasonic have been applied to evaluate defect evolution within a PWR reduced scale (1:5) pressure vessel subjected to cyclic mechanical fatigue test. This experimental activity has been carried out in the frame of the Primary Circuit Component Life Prediction programme. In the time period covered by this report actions were performed as following: (1) Ultrasonic examination by multifrequency acoustic holography to evaluate defect evolution subsequently repair and heat treatment of the R2 vessel carried out in March 1988. For the purpose, measurements were performed both at 0 and 200 bar of internal pressure. As uniformity of the procedures adopted, for calibration and testing, made the results comparable with the previous ones no evidence for significant growing of the examined defects has been found. (2) Acoustic emission monitoring has then been carried out during fatigue test from 416000 to 565000 fatigue cycles. Analysis of a large amount of data has been performed paying particular attention to the distinction between friction phenomena and crack growth in order to obtain a correct diagnosis of flaw evolution. The signal duration distribution and the correlation of AE appearance time versus load cycle phase were considered to characterise stick-slip processes. A general intensification of AE activity has been recorded during this last period of monitoring and previous known AE sources were confirmed together with the appearance of new AE sources some of them correlable with real defects

Examples for monitoring at GKN

International Nuclear Information System (INIS)

Bartonicek, J.; Alt, M.; Manke, A.

1999-01-01

On-line monitoring is carried out in order to ensure integrity of the various plant components of relevance to safety of operation. The original quality of the components has to be safeguarded over their service life by appropriate redundant measures. This belongs to the legal requirements laid down in nuclear engineering codes. Components are damaged in operation only by real operating loads, or effects of the environment conditions. This is why monitoring of the causes of damage mechanisms is given high priority in any concept for ensuring component integrity. The results accumulated so far through the monitoring methods applied at GKN have shown that non-specified, or unspecifiable, loading conditions may be induced by plant operation, and that the available information on the effects, as obtained by in-service inspections, should be supplemented by information drawn from destructive inspections. The comprehensive concept for safeguarding component integrity at GKN is discussed. (orig./CB) [de

Fuel inspection device

International Nuclear Information System (INIS)

Tsuji, Tadashi.

1990-01-01

The fuel inspection device of the present invention has a feature of obtaining an optimum illumination upon fuel rod interval inspection operation in a fuel pool. That is, an illumination main body used underwater is connected to a cable which is led out on a floor. A light control device is attached to the other end of the cable and an electric power cable is connected to the light control device. A light source (for example, incandescent lamp) is incorporated in the casing of the illumination main body, and a diffusion plate is disposed at the front to provide a plane light source. The light control device has a light control knob capable of remote-controlling the brightness of the light of the illumination main body. In the fuel inspection device thus constituted, halation is scarcely caused on the image screen upon inspection of fuels by a submerged type television camera to facilitate control upon inspection. Accordingly, efficiency of the fuel inspection can be improved to shorten the operation time. (I.S.)

Inspection of training activities by the NRC's Office of Inspection and Enforcement

International Nuclear Information System (INIS)

Ruhlman, W.A.

1975-01-01

New requirements in the Code of Federal Regulations, the issuance of new Regulatory Guides and ANSI Standards, have indicated the increased emphasis being placed on training by forces in the Nuclear Industry and the Nuclear Regulatory Commission. A brief description is presented of the functions of the Office of Inspection and Enforcement in the training areas. Three areas are examined: general inspection techniques; training inspection scope; and training inspection bases

OSE inspection of protection program operations field perspective of inspections

International Nuclear Information System (INIS)

Brown, R.W.; Martin, H.R.

1987-01-01

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

Nuclear Technology. Course 28: Welding Inspection. Module 28-6, Process Controls.

Science.gov (United States)

Espy, John

This sixth in a series of ten modules for a course titled Welding Inspection describes procedures review, process monitoring, and weld defect analysis. The module follows a typical format that includes the following sections: (1) introduction, (2) module prerequisites, (3) objectives, (4) notes to instructor/student, (5) subject matter, (6)…

POTENTIAL OF UAV-BASED LASER SCANNER AND MULTISPECTRAL CAMERA DATA IN BUILDING INSPECTION

Directory of Open Access Journals (Sweden)

D. Mader

2016-06-01

Full Text Available 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.

Technical regulation of nondestructive inspection

International Nuclear Information System (INIS)

1995-01-01

It starts with the explanation of definition of nondestructive inspection and qualifications for a inspection. It lists the technical regulations of nondestructive inspections which are radiographic testing, ultrasonic flaw detecting test, liquid penetrant test, magnetic particle inspection, eddy current test visual inspection and leakage test.

STATE INSPECTION METHODOLOGY OF ENVIRONMENTAL REGULATORY ACTIVITY FOCUSED ON THE LIFE CYCLE PROCESSESES

Directory of Open Access Journals (Sweden)

Yuniey Quiala Armenteros

2016-10-01

Full Text Available The Cuban Environmental Regulatory Activity has on the Environmental State Inspection an instrument for control and monitoring of compliance of current legal standards regarding environmental protection and rational use of natural resources. In this research, a design methodology for effective implementation of environmental regulatory activity in Cuba directed to processes is proposed; based on the life cycle assessment and the applicable environmental management standards, including new performance indicators, which form a new tool based on scientific criterions for the Center of Environmental Inspection and Control.

Integration of structural health monitoring solutions onto commercial aircraft via the Federal Aviation Administration structural health monitoring research program

Science.gov (United States)

Swindell, Paul; Doyle, Jon; Roach, Dennis

2017-02-01

The Federal Aviation Administration (FAA) started a research program in structural health monitoring (SHM) in 2011. The program's goal was to understand the technical gaps of implementing SHM on commercial aircraft and the potential effects on FAA regulations and guidance. The program evolved into a demonstration program consisting of a team from Sandia National Labs Airworthiness Assurance NDI Center (AANC), the Boeing Corporation, Delta Air Lines, Structural Monitoring Systems (SMS), Anodyne Electronics Manufacturing Corp (AEM) and the FAA. This paper will discuss the program from the selection of the inspection problem, the SHM system (Comparative Vacuum Monitoring-CVM) that was selected as the inspection solution and the testing completed to provide sufficient data to gain the first approved use of an SHM system for routine maintenance on commercial US aircraft.

The passive seismic aftershock Monitoring system: testing program and preliminary results

International Nuclear Information System (INIS)

Mokhtari, M.

2005-01-01

The paper is dedicated to testing program (phase of the passive seismic aftershock monitoring system with RefTek equipment (Refraction Technology, Inc., USA) for On-Site Inspection purposes that was carried out near Vienna International Centre in 2000. Equipment and applied software are described. Testing results were analyzed; in particular, least needs in maintenance personnel during operation. Development perspectives of passive seismic aftershock monitoring system for On-Site Inspection have been discussed. (author)

Pipe degradation investigations for optimization of flow-accelerated corrosion inspection location selection

International Nuclear Information System (INIS)

Chandra, S.; Habicht, P.; Chexal, B.; Mahini, R.; McBrine, W.; Esselman, T.; Horowitz, J.

1995-01-01

A large amount of piping in a typical nuclear power plant is susceptible to Flow-Accelerated Corrosion (FAC) wall thinning to varying degrees. A typical PAC monitoring program includes the wall thickness measurement of a select number of components in order to judge the structural integrity of entire systems. In order to appropriately allocate resources and maintain an adequate FAC program, it is necessary to optimize the selection of components for inspection by focusing on those components which provide the best indication of system susceptibility to FAC. A better understanding of system FAC predictability and the types of FAC damage encountered can provide some of the insight needed to better focus and optimize the inspection plan for an upcoming refueling outage. Laboratory examination of FAC damaged components removed from service at Northeast Utilities' (NU) nuclear power plants provides a better understanding of the damage mechanisms involved and contributing causes. Selected results of this ongoing study are presented with specific conclusions which will help NU to better focus inspections and thus optimize the ongoing FAC inspection program

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

International Nuclear Information System (INIS)

Lewis, R.K.; Radigan, T.M.

1998-01-01

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

Benchmarking on Inspection Practices. First Triennial Report of the Working Group on Inspection Practices

International Nuclear Information System (INIS)

2017-01-01

The WGIP Nuclear Power Plant (NPP) Observed Inspection Practices Program is intended to promote co-operation and learning among member countries and to collect and provide them with information for improving the effectiveness of existing regulatory inspection practices. This is accomplished by observing how inspections are carried out by other member countries and issuing a WGIP observed inspection report that includes observations (e.g. inspection techniques, obstacles encountered), lessons learnt and potential commendable practices that could be used by a regulatory body. This first triennial report documents the results of a consistency check performed between all six WGIP observed inspection reports and ratifies certain observations, lessons learnt and potential commendable practices identified by WGIP observed inspection participants

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

International Nuclear Information System (INIS)

Moore, F.W.

1986-01-01

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

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

International Nuclear Information System (INIS)

Moore, F.W.

1985-01-01

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% basis after pellet sintering. A feeder will deliver the pellets directly to 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

Surveillance and in-service inspection (SISI) program at FFTF

International Nuclear Information System (INIS)

Conrads, T.J.

1980-01-01

Assurance of the integrity of the sodium coolant pressure boundaries of the Fast Flux Test Facility systems and components is essential for safe operation. A program has been developed to monitor the integrity of the coolant boundaries and certain plant conditions. Specific equipment and features have been designed into the plant for monitoring. The purpose of SISI is to prevent failures or minimize their consequences through early detection. The program which administers the requirements for monitoring applicable plant conditions whose integrity is necessary to protect public health and safety is known as the Surveillance and In-service Inspection (SISI) Program. The SISI program utilizes a wide range of monitoring techniques to ensure that material degradation or structural deficiencies will not result in the loss of the ability to shut down the reactor, cool the reactor core, or cause the release of radioactive material to the environment

In service inspection of pipes based on risk methods

International Nuclear Information System (INIS)

Mendoza G, G.; Viais J, J.; Carmona C, M.

2006-01-01

, 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)

Reliability updating with inspection and monitoring data in deteriorating reinforced concrete slabs

OpenAIRE

Straub, D.

2015-01-01

Corrosion is a common phenomenon in engineering structures; examples include corrosion of the reinforcement in RC structures, corrosion of steel plates in ship hulls or localized corrosion in pipelines. These corrosion mechanisms are generally subject to random spatial variability, due to random changes in in-fluencing factors over space. When assessing the effect of inspections and measurements on the reliability of such structures, it is essential to account for this spatial variability: Du...

Optimized inspection techniques and structural analysis in lifetime management

International Nuclear Information System (INIS)

Aguado, M.T.; Marcelles, I.

1993-01-01

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

Remote inspection system for components installed inside a primary containment vessel of a boiling water reactor

International Nuclear Information System (INIS)

Shimizu, Katsutoshi; Kawai, Katsumi; Ito, Takahiko; Hashimoto, Yuji; Tomizawa, Fumio.

1983-01-01

A remote operation type monitoring system was developed to always enable the watching of the condition of the main equipment installed in the containment vessels of BWRs. It comprises four inspection vehicles suspended by a monorail and pulled with trolley chain, coaxial cables for signal transmission and power supply, and control system. On the inspection vehicles, a television camera, a thermometer, a microphone and a radiation dose rate meter are installed. The performance of the system was confirmed at 60 deg C for several months. Thereafter, the field test was carried out in the Tokai No. 2 Power Station, Japan Atomic Power Co., from December, 1980, to September, 1981. By the continuous monitoring and grasp of operational condition, the preventive maintenance and the improvement of the rate of operation can be expected. Also it is desirable in view of the reduction of radiation exposure of operators. The mechanization of and the labor saving in inspection and maintenance works is necessary because skilled workers will be short. The design and the composition of the system and its tests are reported. (Kako, I.)

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

International Nuclear Information System (INIS)

Lindblom, Lars; Clausen, Jonas; Edvardsson, Karin; Hayenhielm, Madeleine; Hermansson, Helene; Nihlen, Jessica; Palm, Elin; Ruden, Christina; Wikman, Per; Hansson, Sven Ove

2003-04-01

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

Pressurized water reactor inspection procedures

International Nuclear Information System (INIS)

Heinrich, D.; Mueller, G.; Otte, H.J.; Roth, W.

1998-01-01

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.) [de

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 cont...... of probability and statistics for application in structural reliability-based risk inspections....

Assessment of Current Inservice Inspection and Leak Monitoring Practices for Detecting Materials Degradation in Light Water Reactors

Energy Technology Data Exchange (ETDEWEB)

Anderson, Michael T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Simonen, Fredric A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Muscara, Joseph [US Nuclear Regulatory Commission (NRC), Rockville, MD (United States); Doctor, Steven R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kupperman, David S. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-09-01

An assessment was performed to determine the effectiveness of existing inservice inspection (ISI) and leak monitoring techniques, and recommend improvements, as necessary, to the programs as currently performed for light water reactor (LWR) components. Information from nuclear power plant (NPP) aging studies and from the U. S. Nuclear Regulatory Commission’s Generic Aging Lessons Learned (GALL) report (NUREG-1801) was used to identify components that have already experienced, or are expected to experience, degradation. This report provides a discussion of the key aspects and parameters that constitute an effective ISI program and a discussion of the basis and background against which the effectiveness of the ISI and leak monitoring programs for timely detection of degradation was evaluated. Tables based on the GALL components were used to systematically guide the process, and table columns were included that contained the ISI requirements and effectiveness assessment. The information in the tables was analyzed using histograms to reduce the data and help identify any trends. The analysis shows that the overall effectiveness of the ISI programs is very similar for both boiling water reactors (BWRs) and pressurized water reactors (PWRs). The evaluations conducted as part of this research showed that many ISI programs are not effective at detecting degradation before its extent reached 75% of the component wall thickness. This work should be considered as an assessment of NDE practices at this time; however, industry and regulatory activities are currently underway that will impact future effectiveness assessments. A number of actions have been identified to improve the current ISI programs so that degradation can be more reliably detected.

Results of the 5th regular inspection of Unit 1 in the Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

1983-01-01

The 5th regular inspection of Unit 1 in the Hamaoka Nuclear Power Station was carried out from March 27 to July 27, 1982. Inspection was made on the reactor proper, reactor cooling system, instrumentation/control system, radiation control facility, etc. By the examinations of external appearance, leakage, performance, etc., no abnormality was observed. In the regular inspection, personnel exposure dose was all below the permissible level. The works done during the inspection were the following: the replacement of control rod drives, the replacement of core support-plate plugs, the repair of steam piping, steam extraction pipes and feed water heaters, the repair of a waste-liquid concentrator, the installation of barriers and leak detectors, the installation of drain sump monitors in a containment vessel, the replacement of concentrated liquid waste pumps, the employment of type B fuel. (Mori, K.)

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

From PISC to risk informed inspection

International Nuclear Information System (INIS)

Crutzen, S.; Lemaitre, P.; Fabbri, L.

1998-01-01

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)

Inspection device for fuel rod restraint by support lattice of fuel assembly

International Nuclear Information System (INIS)

Hasegawa, Isao; Senga, Masatoshi; Kada, Mitoshi.

1991-01-01

An inspection operation section for disposing fuel assembly vertically at predetermined positions, a control section wired therewith, a moving operation section movable in the direction of X, Y and Z axes by a driving signal sent from the control section are disposed to an inspection section main body. A downward bore scope and a upward bore scope, each of such a size as can be inserted to the gaps between the fuel rods, are disposed while opposing to each other for observing the inside of each of cells from above and below in support lattices of fuel assemblies. High performance television cameras are disposed to each of bore scopes to supply images to monitoring televisions in the control section. Thus, a displacing operation section of the inspection operation section is automatically controlled three-dimensionally, the downward bore scope and the upward bore scope are integrally intruded to the inside of the gaps between the predetermined fuel rods from a required height and stopped at a predetermined position, mounted automatically to a required cell of the support lattice to efficiently observe and inspect the fuel rod restraint. (N.H.)

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

International Nuclear Information System (INIS)

Puri, R.K.; Singh, M.

2006-01-01

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

Eddy current technology for heat exchanger and steam generator tube inspection

Energy Technology Data Exchange (ETDEWEB)

Obrutsky, L.; Lepine, B.; Lu, J.; Cassidy, R.; Carter, J. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2004-07-01

A variety of degradation modes can affect the integrity of both heat exchanger (HX) and balance of plant tubing, resulting in expensive repairs, tube plugging or replacement of tube bundles. One key component for ensuring tube integrity is inspection and monitoring for detection and characterization of the degradation. In-service inspection of HX and balance of plant tubing is usually carried out using eddy current (EC) bobbin coils, which are adequate for the detection of volumetric degradations. However, detection and quantification of additional modes of degradation such as pitting, intergranular attack (IGA), axial cracking and circumferential cracking require specialized probes. The need for timely, reliable detection and characterization of these modes of degradation is especially critical in Nuclear Generating Stations. Transmit-receive single-pass array probes, developed by AECL, offer high defect detectability in conjunction with fast and reliable inspection capabilities. They have strong directional properties, permitting probe optimization for circumferential or axial crack detection. Compared to impedance probes, they offer improved performance in the presence of variable lift-off. This EC technology can help resolve critical detection issues at susceptible areas, such as the rolled-joint transitions at the tubesheet, U-bends and tube-support intersections. This paper provides an overview of the operating principles and the capabilities of advanced ET inspection technology available for HX tube inspection. Examples of recent application of this technology in Nuclear Generating Stations (NGSs) are discussed. (author)

Eddy current technology for heat exchanger and steam generator tube inspection

International Nuclear Information System (INIS)

Obrutsky, L.; Lepine, B.; Lu, J.; Cassidy, R.; Carter, J.

2004-01-01

A variety of degradation modes can affect the integrity of both heat exchanger (HX) and balance of plant tubing, resulting in expensive repairs, tube plugging or replacement of tube bundles. One key component for ensuring tube integrity is inspection and monitoring for detection and characterization of the degradation. In-service inspection of HX and balance of plant tubing is usually carried out using eddy current (EC) bobbin coils, which are adequate for the detection of volumetric degradations. However, detection and quantification of additional modes of degradation such as pitting, intergranular attack (IGA), axial cracking and circumferential cracking require specialized probes. The need for timely, reliable detection and characterization of these modes of degradation is especially critical in Nuclear Generating Stations. Transmit-receive single-pass array probes, developed by AECL, offer high defect detectability in conjunction with fast and reliable inspection capabilities. They have strong directional properties, permitting probe optimization for circumferential or axial crack detection. Compared to impedance probes, they offer improved performance in the presence of variable lift-off. This EC technology can help resolve critical detection issues at susceptible areas, such as the rolled-joint transitions at the tubesheet, U-bends and tube-support intersections. This paper provides an overview of the operating principles and the capabilities of advanced ET inspection technology available for HX tube inspection. Examples of recent application of this technology in Nuclear Generating Stations (NGSs) are discussed. (author)

RIMACS, Reactor Inspection Main Control System

International Nuclear Information System (INIS)

2008-01-01

1 - Description of program or function: RIMACS prepares for automatic inspection files on each inspection item for the reactor. These automatic inspection files provide the data to move RIROB (Reactor Inspection Robot) with laser by interpreting the coordinates of LASPO (Laser Positioner) and the laser detecting device of RIROB in three dimensional space. In addition, when RIROB arrives at the inspecting location, the files provide all values of the manipulator's motions to acquire the ultrasonic data. RIMACS provides various modules in order to perform these complex functions, and the functions are programmed on graphic user interface for the convenience of the user. RIMACS provides various functions, such as insertion of reactor production data, selection of the reactor for inspection, the creation of automatic inspection file, the selection of the inspection item, inspection simulation, and automatic inspection procedures. It also provides all other functions, which are necessary for the inspection, such as operating program download and manual control of LASPO and RIROB, the inspection simulation and the inspection status display by means of the graphic screen, and SODAS (ultra-Sonic Data Acquisition System) drive verification. 2 - Methods: Moving path and operation procedures for inspection robot are generated automatically with Kinematics algorithm. 3 - Restrictions on the complexity of the problem: A graphics display with MS-Window capability is required

Technical objectives of inspection

International Nuclear Information System (INIS)

Sorenson, R.J.; Stewart, K.B.; Schneider, R.A.

1976-01-01

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

Development and Applicability Demonstration of a Remote Inspection Module for Inspection of Reactor Internals in an SFR

International Nuclear Information System (INIS)

Kim, Hoewoong; Joo, Youngsang; Park, Changgyu; Kim, Jongbum; Bae, Jinho

2014-01-01

Since liquid sodium is optically opaque, the ultrasonic inspection technique has been mainly employed for inspection of reactor internals in a Sodium-cooled Fast Reactor (SFR). Until now, two types of ultrasonic sensors have been mainly developed; immersion and waveguide sensors. An immersion sensor can provide a high-resolution image, but it may have problems in terms of reliability and life time because the sensor is exposed to high temperature during inspection. On the other hand, a waveguide sensor can maintain its performance during long-term inspection in high temperature because it installs an ultrasonic transducer in a cold region even though such a high-frequency ultrasonic wave cannot be used owing to the long propagation distance [4-6]. In this work, a remote inspection module employing four 10 m long waveguide sensors was newly developed and several performance tests were carried out in water to demonstrate the applicability of the developed remote inspection module to inspection of reactor internals in an SFR. In this work, a remote inspection module for inspection of reactor internals in an SFR was newly developed. The developed remote inspection module employs four 10 m long waveguide sensors for multiple inspection applications: a horizontal beam waveguide sensor for ranging inspection, two vertical beam waveguide sensors for viewing inspection and a 45 .deg. angle beam waveguide sensor for identification inspection. Several performance tests such as ranging, viewing and identification inspections were carried out for simulated nuclear fuel assembly specimens in water, and the applicability of the developed remote inspection module to inspection of reactor internals in an SFR was demonstrated

Development and Applicability Demonstration of a Remote Inspection Module for Inspection of Reactor Internals in an SFR

Energy Technology Data Exchange (ETDEWEB)

Kim, Hoewoong; Joo, Youngsang; Park, Changgyu; Kim, Jongbum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Bae, Jinho [National Fusion Research Institute, Daejeon (Korea, Republic of)

2014-05-15

Since liquid sodium is optically opaque, the ultrasonic inspection technique has been mainly employed for inspection of reactor internals in a Sodium-cooled Fast Reactor (SFR). Until now, two types of ultrasonic sensors have been mainly developed; immersion and waveguide sensors. An immersion sensor can provide a high-resolution image, but it may have problems in terms of reliability and life time because the sensor is exposed to high temperature during inspection. On the other hand, a waveguide sensor can maintain its performance during long-term inspection in high temperature because it installs an ultrasonic transducer in a cold region even though such a high-frequency ultrasonic wave cannot be used owing to the long propagation distance [4-6]. In this work, a remote inspection module employing four 10 m long waveguide sensors was newly developed and several performance tests were carried out in water to demonstrate the applicability of the developed remote inspection module to inspection of reactor internals in an SFR. In this work, a remote inspection module for inspection of reactor internals in an SFR was newly developed. The developed remote inspection module employs four 10 m long waveguide sensors for multiple inspection applications: a horizontal beam waveguide sensor for ranging inspection, two vertical beam waveguide sensors for viewing inspection and a 45 .deg. angle beam waveguide sensor for identification inspection. Several performance tests such as ranging, viewing and identification inspections were carried out for simulated nuclear fuel assembly specimens in water, and the applicability of the developed remote inspection module to inspection of reactor internals in an SFR was demonstrated.

Inspection Strategies for Concrete Bridges

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Thoft-Christensen, Palle

1989-01-01

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....

9 CFR 381.76 - Post-mortem inspection, when required; extent; traditional, Streamlined Inspection System (SIS...

Science.gov (United States)

2010-01-01

...; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS... (NELS) Inspection System, both of which shall be used only for broilers and cornish game hens; the New... Inspection. (i) The SIS shall be used only for broilers and cornish game hens if: (a) The Administrator...

Inspection of disposal canisters components

International Nuclear Information System (INIS)

Pitkaenen, J.

2013-12-01

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

RBI - Risk Based Inspection: new technologies and methods applied to inspections of FPSO (Floating Production, Storage and Offloading Vessel) hull; IBR - Inspecao Baseada em Risco: novas tecnologias e metodos aplicados as inspecoes de casco de FPSOs

Energy Technology Data Exchange (ETDEWEB)

Farias, Bruno de; Figueiredo, Eduardo; Luiz, Marcio [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Meurer, Gustavo; Duarte, Romulo; Oliveira, Thais; Krzonkalla, Viviane [ABS Consulting, Rio de Janeiro, RJ (Brazil)

2008-07-01

With the aging of the FPSO's, which are fundamental to the operation Offshore, better techniques and technologies must be applied to assess more accurately the actual efficiency and structural conditions of producing unit. With the emergence of new engineering techniques and equipment and methods of structural inspection, is now possible to use these new technologies to better manage risk and reliability of the structure of the FPSO, with that, the inspections and methods are more rational and efficient. The Risk-Based Inspection is the tool for monitoring operation of industrial plants with systemic use of technology in conjunction with risk analysis and reliability. His concept is applicable to various branches of industry. The companies began their implementation of oil by refineries. The group of ABS Consulting with PETROBRAS has been developing and implementing these new technologies in inspections of hulls of FPSO's. Applied successfully in the units of the Campos basin, these methods are used by the group of Risk-Based Inspection to improve the efficiency of all the steps involved with the structural integrity of the unit. (author)

Radiation control in the nondestructive inspection

International Nuclear Information System (INIS)

Kariya, Yukihiro

1982-01-01

In the early days of radiation nondestructive inspection about ten years ago, the loss of radiation sources and careless radiation exposure gave the impression of radiography inspection being immediately slipshod management. In this problem, the peculiar nature of the business in this field is involved. In Nondestructive Inspection Co., Ltd., besides the safety management of radioisotopes, the radiation exposure control of personnel in the regular inspection of nuclear power plants has become increasingly important. The following matters are described: radiation utilization in nondestructive inspection (X- and #betta#-ray radiography, #betta#-ray leak test on shield), radiation control problems in nondestructive inspection business (the peculiar aspects of the business, the analysis of the incidents related with nondestructive inspection), and the practice of radiation control in nondestructive inspection in Nondestructive Inspection Co., Ltd. (Mori, K.)

PWR reactor vessel in-service-inspection according to RSEM

International Nuclear Information System (INIS)

Algarotti, Marc; Dubois, Philippe; Hernandez, Luc; Landez, Jean Paul

2006-01-01

Nuclear services experience Framatome ANP (an AREVA and Siemens company) has designed and constructed 86 Pressurized Water Reactors (PWR) around the world including the three units lately commissioned at Ling Ao in the People's Republic of China and ANGRA 2 in Brazil; the company provided general and specialized outage services supporting numerous outages. Along with the American and German subsidiaries, Framatome ANP Inc. and Framatome ANP GmbH, Framatome ANP is among the world leading nuclear services providers, having experience of over 500 PWR outages on 4 continents, with current involvement in more than 50 PWR outages per year. Framatome ANP's experience in the examinations of reactor components began in the 1970's. Since then, each unit (American, French and German companies) developed automated NDT inspection systems and carried out pre-service and ISI (In-Service Inspections) using a large range of NDT techniques to comply with each utility expectations. These techniques have been validated by the utilities and the safety authorities of the countries where they were implemented. Notably Framatome ANP is fully qualified to provide full scope ISI services to satisfy ASME Section XI requirements, through automated NDE tasks including nozzle inspections, reactor vessel head inspections, steam generator inspections, pressurizer inspections and RPV (Reactor Pressure Vessel) inspections. Intercontrole (Framatome ANP subsidiary dedicated in supporting ISI) is one of the leading NDT companies in the world. Its main activity is devoted to the inspection of the reactor primary circuit in French and foreign PWR Nuclear Power Plants: the reactor vessel, the steam generators, the pressurizer, the reactor internals and reactor coolant system piping. NDT methods mastered by Intercontrole range from ultrasonic testing to eddy current and gamma ray examinations, as well as dye penetrant testing, acoustic monitoring and leak testing. To comply with the high requirements of

Results of activities at the upgraded inspection and repair facility in Temelin NPP

International Nuclear Information System (INIS)

Samojlov, O.B.; Romanov, A.I.; Sholin, E.V.; Molchanov, V.L.

2010-01-01

Based on a contract signed between JSC TVEL and CEZ a.s., JSC TVEL provided additional equipment for the VVantage6 FA inspection and repair facility at the Temelin NPP to switch to TVSA-T inspection and repair. JSC TVEL analyzed the equipment (modules) of the Temelin NPP inspection and repair facility with focus on the compatibility of the current facility design and modules with the TVSA-T design. Based on the analysis, a set of modules and systems was identified, which were developed and manufactured or upgraded to ensure TVSA-T inspection and repair in the Temelin NPP facility. The set of modules and systems for TVSA-T inspection and repair included: (i) A guide to point the FA headpiece manipulator at the guide thimbles and to point the Cladding Integrity Monitoring (CIM) manipulator (which is part of the CIM System) at the upper end plugs; (ii) A guide grip to install the guide on the facility workstation table; (iii) An FA headpiece manipulator to detach, remove, install and attach the TVSA-T headpiece; (iv) A jig to point the upgraded fuel rod extraction tool at the upper end plug of the extracted fuel rod; (v) A colette and a locking tube to extract a fuel rod and install a displacer using the fuel rod extraction tool, which is part of the Temelin facility; (vi) A CIM system to detect leaky fuel rods. Pictures of the modules and of the fuel rod extraction tools are displayed, and the CIM system is described. The principle to detect leaky fuel rods is explained. In 2010, TVSA-T mockup repair tests were conducted in the Temelin NPP facility using earlier manufactured modules and systems. The following operations were performed during the tests: detaching and removal of the TVSA-T headpiece; detection of leaky fuel rod mockups; extraction of the fuel rod mockup and installation of the displacer in its place; installation and attaching of the TVSA-T headpiece. The installation of the following 2 TV systems is planned for 2011: a color non

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

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

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

Estimation of inspection effort

International Nuclear Information System (INIS)

Mullen, M.F.; Wincek, M.A.

1979-06-01

An overview of IAEA inspection activities is presented, and the problem of evaluating the effectiveness of an inspection is discussed. Two models are described - an effort model and an effectiveness model. The effort model breaks the IAEA's inspection effort into components; the amount of effort required for each component is estimated; and the total effort is determined by summing the effort for each component. The effectiveness model quantifies the effectiveness of inspections in terms of probabilities of detection and quantities of material to be detected, if diverted over a specific period. The method is applied to a 200 metric ton per year low-enriched uranium fuel fabrication facility. A description of the model plant is presented, a safeguards approach is outlined, and sampling plans are calculated. The required inspection effort is estimated and the results are compared to IAEA estimates. Some other applications of the method are discussed briefly. Examples are presented which demonstrate how the method might be useful in formulating guidelines for inspection planning and in establishing technical criteria for safeguards implementation

Bridging of inspection with corrosion management

International Nuclear Information System (INIS)

Zamaluddin Ali; Mohd Hawari Hassan; Rohana Jaafar

2009-01-01

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)

Three Sisters Dam: Investigations and monitoring

International Nuclear Information System (INIS)

Slopek, R.J.; Courage, L.J.R.; Keys, R.A.

1990-01-01

The geotechnical investigations, monitoring and interpretation of data associated with the evaluation of the Three Sisters Dam, which has been suffering from excessive seepage and is in need of enhancement, are outlined. The Three Sisters Dam is located in the continental ranges of the Rocky Mountains in Alberta, impounding the Spray Reservoir, and is founded on 60 m of interbedded sand, gravel, silt and clay layers. The computer code PC-SEEP was used to evaluate seepage. Details are provided of drilling, ground-penetrating radar surveys, seismic surveys, penstock inspection, sinkhole activity, piezometer monitoring, silt wells, settlement monuments, and tailrace monitoring. The intensive investigations of the foundations showed that they consist of a complex formation of interfingered stratified layers and leases of talus and glaciofluvial deposits. Due to the depth and nature of these materials drill hole penetration was limited to the use of the Becker hammer. This equipment successfully delineated the major soil horizons of the foundation. The continued information attained from inspection, drilling, testing, radar surveys, seismic work, monitoring of piezometers, leakage, silt wells and settlement monuments indicated that there are no large voids within the foundation of the dam. 2 refs., 12 figs

40 CFR 63.773 - Inspection and monitoring requirements.

Science.gov (United States)

2010-07-01

... the condenser design analysis and may be supplemented by the control device manufacturer's... continuous monitoring system shall be designed and operated so that a determination can be made on whether... or process heater with a design heat input capacity equal to or greater than 44 megawatts. (3) The...

Pattern centric design based sensitive patterns and process monitor in manufacturing

Science.gov (United States)

Hsiang, Chingyun; Cheng, Guojie; Wu, Kechih

2017-03-01

When design rule is mitigating to smaller dimension, process variation requirement is tighter than ever and challenges the limits of device yield. Masks, lithography, etching and other processes have to meet very tight specifications in order to keep defect and CD within the margins of the process window. Conventionally, Inspection and metrology equipments are utilized to monitor and control wafer quality in-line. In high throughput optical inspection, nuisance and review-classification become a tedious labor intensive job in manufacturing. Certain high-resolution SEM images are taken to validate defects after optical inspection. These high resolution SEM images catch not only optical inspection highlighted point, also its surrounding patterns. However, this pattern information is not well utilized in conventional quality control method. Using this complementary design based pattern monitor not only monitors and analyzes the variation of patterns sensitivity but also reduce nuisance and highlight defective patterns or killer defects. After grouping in either single or multiple layers, systematic defects can be identified quickly in this flow. In this paper, we applied design based pattern monitor in different layers to monitor process variation impacts on all kinds of patterns. First, the contour of high resolutions SEM image is extracted and aligned to design with offset adjustment and fine alignment [1]. Second, specified pattern rules can be applied on design clip area, the same size as SEM image, and form POI (pattern of interest) areas. Third, the discrepancy of contour and design measurement at different pattern types in measurement blocks. Fourth, defective patterns are reported by discrepancy detection criteria and pattern grouping [4]. Meanwhile, reported pattern defects are ranked by number and severity by discrepancy. In this step, process sensitive high repeatable systematic defects can be identified quickly Through this design based process pattern

Gentilly 2 steam generators Spring 2000 outage: tubesheet waterlance cleaning and inspection; upper bundle inspection

International Nuclear Information System (INIS)

Akeroyd, J.K.; Plante, S.

2000-01-01

A review of the secondary side maintenance activities recently completed during the Gentilly 2 Annual Spring 2000 Maintenance Outage. Activities included: 1) Tubesheet intertube waterlance cleaning and visual inspection, 2) First tube support plate, in-bundle visual inspection of the hot leg, and 3) Upper bundle tube support plate visual inspection. A description of the waterlancing and inspection equipment and setup in the RB at Gentilly 2 is provided. Several innovative techniques were successfully employed and yielded savings in critical path duration, labour and personnel radiation dose. These included accessing the SG tubesheet region through one handhole only and sludge removal utilizing the SG blowdown system. Plant personnel judged tubesheet sludge removal successful. Before and after results of the cleaning process along with samples of the visual inspection results are provided. Inspection of the first support plate, which was a repeat of an inspection done in 1997, was conducted along with an in-bundle inspection of the upper tube supports. Results are presented along with a discussion of the implications for future steam generator maintenance. (author)

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

Energy Technology Data Exchange (ETDEWEB)

Engel, Ronald E; Randecker, Victor; Johnson, Wesley [Food Safety and Inspection Service, United States Department of Agriculture (United States)

1989-09-01

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.

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

International Nuclear Information System (INIS)

Engel, Ronald E.; Randecker, Victor; Johnson, Wesley

1989-01-01

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

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

International Nuclear Information System (INIS)

Curiel, M.; Palomo, M. J.; Rodriguez, M.; Arnaldos, A.

2010-10-01

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)

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)

Results of automatic system implementation for Cofrentes power plant detection system LPRM inspection execution

Energy Technology Data Exchange (ETDEWEB)

Palomo, M., E-mail: mpalomo@iqn.upv.es [Departamento de Ingenieria Quimica y Nuclear, Universidad Politecnica de Valencia (Spain); Urrea, M., E-mail: matias.urrea@iberdrola.es [C.N.Cofrentes - Iberdrola Generacion S.A., Valencia (Spain); Curiel, M., E-mail: m.curiel@lainsa.com [LAINSA, Grupo Dominguis, Valencia (Brazil); Arnaldos, A., E-mail: a.arnaldos@titaniast.com [TITANIA Servicios Teconologicos, Valencia (Spain)

2011-07-01

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's test system has been developed and it consists in a software application and data acquisition hardware that performs automatically the complete detection system process: refueling, storage and operation inspection: Ramp voltage generation, measured voltage Plateaux evaluation, qualification report emission; historical analysis to scan burn evolution. The inspections differentiations are developed by the different specifications that it has to fulfil: 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's substitution. Storage inspection: it is made to check the correct functioning and isolation losses before being installed in the core during refueling. Refueling inspection: it is checked that storage LPRM's installation is correct and that they are ready for new fuel cycle. The software application LPRM's Test has been developed by National Instruments LabVIEW, and it performs the following actions: Protocol IEEE-488 (GPIB) control of the source KEITHLEY 237. This source generates the ramp voltage and measure voltage; information acquisition of storage, process and source, identifying LPRM and realization conditions of the same; data analysis and conditions report, historical comparative analysis. (author)

40 CFR 63.7917 - What are my inspection and monitoring requirements for transfer systems?

Science.gov (United States)

2010-07-01

... annually inspect the unburied portion of pipeline and all joints for leaks and other defects. In the event that a defect is detected, you must repair the leak or defect according to the requirements of... days after detection and repair shall be completed as soon as possible but no later than 45 calendar...

Results of the 4th regular inspection in Unit 1 of the Mihama Nuclear Power Station

International Nuclear Information System (INIS)

1981-01-01

The 4th regular inspection of Unit 1 in the Mihama Nuclear Power Station was made from July, 1975, to December, 1980, on its reactor and associated facilities. The respective stages of inspection during the years are described. The inspection by external appearance examination, disassembling leakage inspection and performance tests indicated crackings in piping for fuel-replacement water tank, the container penetration of recirculation pipe for residual-heat removal, and main steam-relief valve, and leakage in one fuel assembly. Radiation exposure of the personnel during the inspection was less than the permissible dose. Radiation exposure data for the personnel are given in tables. The improvements and repairs done accordingly were as follows: reapir of the piping for a fuel-replacement tank and recirculation piping for residual-heat removal, replacement of the main steam-relief valve, plugging of heating tubes for the steam-generator, replacement of pins and covers for control-rod guide pipes, improvement of safety protection system and installation of rare gas monitor. (J.P.N.)

Industrial chimney monitoring - contemporary methods

Science.gov (United States)

Kaszowska, Olga; Gruchlik, Piotr; Mika, Wiesław

2018-04-01

The paper presents knowledge acquired during the monitoring of a flue-gas stack, performed as part of technical and scientific surveillance of mining activity and its impact on industrial objects. The chimney is located in an area impacted by mining activity since the 1970s, from a coal mine which is no longer in existence. In the period of 2013-16, this area was subject to mining carried out by a mining entrepreneur who currently holds a license to excavate hard coal. Periodic measurements of the deflection of the 113-meter chimney are performed using conventional geodetic methods. The GIG used 3 methods to observe the stack: landbased 3D laser scanning, continuous deflection monitoring with a laser sensor, and drone-based visual inspections. The drone offered the possibility to closely inspect the upper sections of the flue-gas stack, which are difficult to see from the ground level.

Study on the inspection item and inspection method of HTGR fuel

International Nuclear Information System (INIS)

Na, Sang Ho; Kim, Y. K.; Jeong, K. C.; Oh, S. C.; Cho, M. S.; Kim, Y. M.; Lee, Y. W.

2006-01-01

The type of HTGR(High Temperature Gas-cooled Reactor) fuel is different according to the reactor type. Generally the HTGR fuel has two types. One is a block type, which is manufactured in Japan or America. And the other is a pebble type, which is manufactured in China. Regardless of the fuel type, the fuel manufacturing process started from the coated particle, which is consisted of fuel kernel and the 4 coating layers. Korea has a plan to fabricate a HTGR fuel in near future. The appropriate quality inspection standards are requested to produce a sound and reliable coated particle for HTGR fuel. Therefore, the inspection items and the inspection methods of HTGR fuel between Japan and China, which countries have the manufacturing process, are investigated to establish a proper inspection standards of our product characteristics

Results of the 6th regular inspection of No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

Anon.

1985-01-01

The 6th periodical inspection on Unit 1 in the Mihama Power Station was made for the period of July to December 1984. Inspection was made in the following: reactor proper, reactor cooling system, instrumentation and control system, radiation control facility, etc. By external appearance observation, disassembly, performance test, etc. there were observed no abnormalities. Personnel radiation exposure doses during the inspection were below the permissible level. The following modification etc. works were done in the periodical inspection: replacement of the accumulator safety valve, replacement of the out-reactor nuclear instrumentation panel, installation of accident-time monitors, replacement of the control-rod cluster guide tube support pins, alteration in the fuel enrichment. (Mori, K.)

The Ontario hydro low pressure turbine disc inspection program automated ultrasonic inspection systems - an overview

International Nuclear Information System (INIS)

Huggins, J.W.; Chopcian, M.; Grabish, M.

1990-01-01

An overview of the Ontario Hydro Low Pressure Turbine Disc Inspection Program is presented. The ultrasonic inspection systems developed in-house to inspect low pressure turbine discs at Pickering and Bruce Nuclear Generating stations are described. Three aspects of the program are covered: PART I - Background to inspection program, disc cracking experience, and development of an in-house inspection capability: PART II - System development requirements; ultrasonic equipment, electromechanical subsystems and instrumentation console: PART III - Customized software for flaw detection, sizing, data acquisition/storage, advanced signal processing, reports, documentation and software based diagnostics

An Explosion Aftershock Model with Application to On-Site Inspection

Science.gov (United States)

Ford, Sean R.; Labak, Peter

2016-01-01

An estimate of aftershock activity due to a theoretical underground nuclear explosion is produced using an aftershock rate model. The model is developed with data from the Nevada National Security Site, formerly known as the Nevada Test Site, and the Semipalatinsk Test Site, which we take to represent soft-rock 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 inform the Seismic Aftershock Monitoring System (SAMS) deployment in a potential Comprehensive Test Ban Treaty On-Site Inspection (OSI), by giving the OSI team 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 apply the hard-rock model to a M5 event and combine it with the very sensitive detection threshold for OSI sensors to show that tens of events per day are expected up to a month after an explosion measured several kilometers away.

A Novel Method of Autonomous Inspection for Transmission Line based on Cable Inspection Robot LiDAR Data

Directory of Open Access Journals (Sweden)

Xinyan Qin

2018-02-01

Full Text Available With the growth of the national economy, there is increasing demand for electricity, which forces transmission line corridors to become structurally complicated and extend to complex environments (e.g., mountains, forests. It is a great challenge to inspect transmission line in these regions. To address these difficulties, a novel method of autonomous inspection for transmission line is proposed based on cable inspection robot (CIR LiDAR data, which mainly includes two steps: preliminary inspection and autonomous inspection. In preliminary inspection, the position and orientation system (POS data is used for original point cloud dividing, ground point filtering, and structured partition. A hierarchical classification strategy is established to identify the classes and positions of the abnormal points. In autonomous inspection, CIR can autonomously reach the specified points through inspection planning. These inspection targets are imaged with PTZ (pan, tilt, zoom cameras by coordinate transformation. The feasibility and effectiveness of the proposed method are verified by test site experiments and actual line experiments, respectively. The proposed method greatly reduces manpower and improves inspection accuracy, providing a theoretical basis for intelligent inspection of transmission lines in the future.

OSE inspections: A different perspective

International Nuclear Information System (INIS)

Ware, J.H.

1987-01-01

The Office of Security Evaluation (OSE) is a staff activity of the Assistant Secretary for Defense Programs (ASDP) and is responsible for the conduct of an inspection and evaluation program. The OSE Inspection Division conducts assessments of the effectiveness of Department of Energy (DOE) Safeguards and Security policies and protection programs. The inspections are conducted by OSE Inspectors and Support Specialists. Prior to the author's participation in the inspection of the San Francisco Operations Office, a DOE Field Office employee had never played an active role in an OSE Inspection of another field office. This paper discloses his experience as an OSE Inspector

40 CFR 63.695 - Inspection and monitoring requirements.

Science.gov (United States)

2010-07-01

... have detached from the roof rim; holes, tears, or other openings are visible in the seal fabric; the... in the rim seal or seal fabric of the floating roof; a rim seal detached from the floating roof; all... monitoring of a piece of air pollution control equipment in accordance with the applicable provisions of this...

Review of fiber optic methods for strain monitoring and non-destructive testing

NARCIS (Netherlands)

Bruinsma, A.J.A.

1989-01-01

A number of fiber optic methods has been developed for the inspection of critical components of mechanical structures. For inspection from a remote location various methods have been developed for the detection of cracks and strain. Some of these monitoring methods use a fiber mesh or OTDR

Packaging supplier inspection guide

International Nuclear Information System (INIS)

Stromberg, H.M.; Gregg, R.E.; Kido, C.; Boyle, C.D.

1991-05-01

This is document is a guide for conducting quality assurance inspections of transportations packaging suppliers, where suppliers are defined as designers, fabricators, distributors, users, or owners of transportation packaging. This document can be used during an inspection to determine regulatory compliance within the requirements of 10 Code of Federal Regulations, Part 71, Subpart H (10 CFR 71.101--71.135). The guidance described in this document provides a framework for an inspection. It provides the inspector with the flexibility to adapt the methods and concepts presented here to meet the needs of the particular facility being inspected. The guide was developed to ensure a structured and consistent approach for inspections. The method treats each activity at a supplier facility as a separate entity (or functional element), and combines the activities within the framework of an ''inspection tree.'' The method separates each functional element into several areas of performance and then identifies guidelines, based on regulatory requirements, to be used to qualitatively rate each area. This document was developed to serve as a field manual to facilitate the work of inspectors. 1 ref., 1 fig., 5 tabs

Periodic and in-service inspection programs

International Nuclear Information System (INIS)

Dinu, M.

2000-01-01

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

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).

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.

Technology of remote nuclear activity monitoring for national safeguards

International Nuclear Information System (INIS)

Kwack, Eun Ho; Kim, B. K.; Kim, J. S.; Yoon, W. K.; Kim, J. S.; Kim, J. S.; Cha, H. R.; Na, W. W.; Choi, Y. M.

2001-07-01

This project mainly focused on technical development on remote monitoring. It covers optical fiber scintillator to be used as NDA sensor to targets to be applied. Optical fiber scintillator was tested at the high radioactive environment. It is the first try in its kind for spent fuel measurement. It is confirmed that optical fiber sensor can be used for safeguards verification. Its feasibility for spent fuel storage silo at Wolsong reactor was studied. And to optimize remote transmission cost which can be regarded as a major barrier, virtual private network was studied for possible application for safeguards purpose. It can drastically reduce transmission cost and upgrade information surety. As target for remote monitoring, light water reactor and heavy water reactor were feasibly studied. Especially heavy water reactor has much potential for reduction of inspection efforts if remote monitoring is introduced. In overall remote monitoring can play a pivotal role to streamline safeguards inspection

Enabling inspection solutions for future mask technologies through the development of massively parallel E-Beam inspection

Science.gov (United States)

Malloy, Matt; Thiel, Brad; Bunday, Benjamin D.; Wurm, Stefan; Jindal, Vibhu; Mukhtar, Maseeh; Quoi, Kathy; Kemen, Thomas; Zeidler, Dirk; Eberle, Anna Lena; Garbowski, Tomasz; Dellemann, Gregor; Peters, Jan Hendrik

2015-09-01

The new device architectures and materials being introduced for sub-10nm manufacturing, combined with the complexity of multiple patterning and the need for improved hotspot detection strategies, have pushed current wafer inspection technologies to their limits. In parallel, gaps in mask inspection capability are growing as new generations of mask technologies are developed to support these sub-10nm wafer manufacturing requirements. In particular, the challenges associated with nanoimprint and extreme ultraviolet (EUV) mask inspection require new strategies that enable fast inspection at high sensitivity. The tradeoffs between sensitivity and throughput for optical and e-beam inspection are well understood. Optical inspection offers the highest throughput and is the current workhorse of the industry for both wafer and mask inspection. E-beam inspection offers the highest sensitivity but has historically lacked the throughput required for widespread adoption in the manufacturing environment. It is unlikely that continued incremental improvements to either technology will meet tomorrow's requirements, and therefore a new inspection technology approach is required; one that combines the high-throughput performance of optical with the high-sensitivity capabilities of e-beam inspection. To support the industry in meeting these challenges SUNY Poly SEMATECH has evaluated disruptive technologies that can meet the requirements for high volume manufacturing (HVM), for both the wafer fab [1] and the mask shop. Highspeed massively parallel e-beam defect inspection has been identified as the leading candidate for addressing the key gaps limiting today's patterned defect inspection techniques. As of late 2014 SUNY Poly SEMATECH completed a review, system analysis, and proof of concept evaluation of multiple e-beam technologies for defect inspection. A champion approach has been identified based on a multibeam technology from Carl Zeiss. This paper includes a discussion on the

Evaluation of NRC maintenance team inspection reports for managing aging

International Nuclear Information System (INIS)

Fresco, A.; Gunther, W.

1991-01-01

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

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.

Framework for Structural Online Health Monitoring of Aging and Degradation of Secondary Systems due to some Aspects of Erosion

Energy Technology Data Exchange (ETDEWEB)

Gribok, Andrei [Idaho National Lab. (INL), Idaho Falls, ID (United States); Patnaik, Sobhan [Idaho National Lab. (INL), Idaho Falls, ID (United States); Williams, Christian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pattanaik, Marut [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kanakala, Raghunath [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

This report describes the current state of research related to critical aspects of erosion and selected aspects of degradation of secondary components in nuclear power plants. The report also proposes a framework for online health monitoring of aging and degradation of secondary components. The framework consists of an integrated multi-sensor modality system which can be used to monitor different piping configurations under different degradation conditions. The report analyses the currently known degradation mechanisms and available predictive models. Based on this analysis, the structural health monitoring framework is proposed. The Light Water Reactor Sustainability Program began to evaluate technologies that could be used to perform online monitoring of piping and other secondary system structural components in commercial NPPs. These online monitoring systems have the potential to identify when a more detailed inspection is needed using real-time measurements, rather than at a pre-determined inspection interval. This transition to condition-based, risk informed automated maintenance will contribute to a significant reduction of operations and maintenance costs that account for the majority of nuclear power generation costs. There is unanimous agreement between industry experts and academic researchers that identifying and prioritizing inspection locations in secondary piping systems (for example, in raw water piping or diesel piping) would eliminate many excessive in-service inspections. The proposed structural health monitoring framework takes aim at answering this challenge by combining long-range guided wave technologies with other monitoring techniques, which can significantly increase the inspection length and pinpoint the locations that degraded the most. More widely, the report suggests research efforts aimed at developing, validating, and deploying online corrosion monitoring techniques for complex geometries, which are pervasive in NPPs.

Framework for Structural Online Health Monitoring of Aging and Degradation of Secondary Systems due to some Aspects of Erosion

International Nuclear Information System (INIS)

Gribok, Andrei; Patnaik, Sobhan; Williams, Christian; Pattanaik, Marut; Kanakala, Raghunath

2016-01-01

This report describes the current state of research related to critical aspects of erosion and selected aspects of degradation of secondary components in nuclear power plants. The report also proposes a framework for online health monitoring of aging and degradation of secondary components. The framework consists of an integrated multi-sensor modality system which can be used to monitor different piping configurations under different degradation conditions. The report analyses the currently known degradation mechanisms and available predictive models. Based on this analysis, the structural health monitoring framework is proposed. The Light Water Reactor Sustainability Program began to evaluate technologies that could be used to perform online monitoring of piping and other secondary system structural components in commercial NPPs. These online monitoring systems have the potential to identify when a more detailed inspection is needed using real-time measurements, rather than at a pre-determined inspection interval. This transition to condition-based, risk informed automated maintenance will contribute to a significant reduction of operations and maintenance costs that account for the majority of nuclear power generation costs. There is unanimous agreement between industry experts and academic researchers that identifying and prioritizing inspection locations in secondary piping systems (for example, in raw water piping or diesel piping) would eliminate many excessive in-service inspections. The proposed structural health monitoring framework takes aim at answering this challenge by combining long-range guided wave technologies with other monitoring techniques, which can significantly increase the inspection length and pinpoint the locations that degraded the most. More widely, the report suggests research efforts aimed at developing, validating, and deploying online corrosion monitoring techniques for complex geometries, which are pervasive in NPPs.

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.

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

International Nuclear Information System (INIS)

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.

Monitor for safety engineering facility

International Nuclear Information System (INIS)

Sato, Akira; Kaneda, Mitsunori.

1982-01-01

Purpose: To improve the reactor safety and decrease misoperation upon periodical inspection by instantly obtaining the judgement for the stand-by states in engineering safety facilities of a nuclear power plant. Constitution: Process inputs representing the states of valves, pumps, flowrates or the likes of the facility are gathered into an input device and inputted to a status monitor. The status of the facility inputted to the input device are judged for each of the inputs in a judging section and recognized as a present system stand-by pattern of the system (Valve) to be inspected. While on the other hand, a normal system stand-by pattern previously stored in a memory unit is read out by an instruction from an operator console and judged by comparison with the system stand-by pattern in a comparison section. The results are displayed on a display device. Upon periodical inspection, inspection procedures stored in the memory unit are displayed on the display device by the instruction from the operator console. (Seki, T.)

Piping inspection round robin

International Nuclear Information System (INIS)

Heasler, P.G.; Doctor, S.R.

1996-04-01

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

Coke drums inspection and evaluation using stress and strain analysis techniques

Energy Technology Data Exchange (ETDEWEB)

Haraguchi, Marcio Issamu [Tricom Tecnologia e Servicos de Manutencao Industrial Ltda., Piquete, SP (Brazil); Samman, Mahmod [Houston Engineering Solutions, Houston, TX (United States); Tinoco, Ediberto Bastos; Marangone, Fabio de Castro; Silva, Hezio Rosa da; Barcelos, Gustavo de Carvalho [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)

2012-07-01

Coke drums deform due to a complex combination of mechanical and thermal cyclic stresses. Bulges have progressive behavior and represent the main maintenance problem related to these drums. Bulge failure typically result in through-wall cracks, leaks, and sometimes fires. Such failures generally do not represent a great risk to personnel. Repairs needed to maintain reliability of these vessels might require extensive interruption to operation which in turn considerably impacts the profitability of the unit. Therefore the condition, progression and severity of these bulges should be closely monitored. Coke drums can be inspected during turnaround with 3D Laser Scanning and Remote Visual Inspection (RVI) tools, resulting in a detailed dimensional and visual evaluation of the internal surface. A typical project has some goals: inspect the equipment to generate maintenance or inspection recommendations, comparison with previous results and baseline data. Until recently, coke drum structural analysis has been traditionally performed analyzing Stress Concentration Factors (SCF) thought Finite Element Analysis methods; however this technique has some serious technical and practical limitations. To avoid these shortcomings, the new strain analysis technique PSI (Plastic Strain Index) was developed. This method which is based on API 579/ ASME FFS standard failure limit represents the state of the art of coke drum bulging severity assessment has an excellent correlation with failure history. (author)

Quality assurance for IAEA inspection planning

International Nuclear Information System (INIS)

Markin, J.T.

1986-01-01

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

Recent activities on clearance in IAEA and clearance automatic laser inspection system (CLALIS)

International Nuclear Information System (INIS)

Hattori, Takatoshi; Sasaki, Michiya

2005-01-01

Exemption levels for bulk amounts of materials have been described in RS-G-1.7 published as a safety guide in IAEA on August 2004. In Japan, the Nuclear Safety Commission adopted the RS-G-1.7 values as Japanese clearance levels after the careful review of dose assessment results. After completing revises of regulatory laws in relation to clearance level, solid wastes from decommissioning and operating nuclear power plants will be targets of clearance inspection. In CRIEPI, Clearance Automatic Laser Inspection System (CLALIS) has been developed, which can give high reliability and objectivity to the measurement data. The CLALIS is a new monitoring system coupling with 3D laser shape measurement, Monte-Carlo calculation and gamma measurement techniques, which can keep a high accuracy in the measurement data using an automatic correction technique for self-shielding effects of metal waste itself and is expected to apply as a practical use in actual clearance inspections. (author)

In-service inspection techniques

International Nuclear Information System (INIS)

Backfisch, W.; Zipser, R.R.

1980-01-01

The owner of a nuclear power plant (NPP) is obligated and interested to maintain - by regular maintenance and in-service inspections - the operational safety and availability of the plant for the subsequent operating period in a condition, as is specified as the basis of the erection and the last operational permits. In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor or on a boiling-water reactor) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

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.

Industrial chimney monitoring - contemporary methods

Directory of Open Access Journals (Sweden)

Kaszowska Olga

2018-01-01

Full Text Available The paper presents knowledge acquired during the monitoring of a flue-gas stack, performed as part of technical and scientific surveillance of mining activity and its impact on industrial objects. The chimney is located in an area impacted by mining activity since the 1970s, from a coal mine which is no longer in existence. In the period of 2013-16, this area was subject to mining carried out by a mining entrepreneur who currently holds a license to excavate hard coal. Periodic measurements of the deflection of the 113-meter chimney are performed using conventional geodetic methods. The GIG used 3 methods to observe the stack: landbased 3D laser scanning, continuous deflection monitoring with a laser sensor, and drone-based visual inspections. The drone offered the possibility to closely inspect the upper sections of the flue-gas stack, which are difficult to see from the ground level.

Detailed simulation of ultrasonic inspections

International Nuclear Information System (INIS)

Chaplin, K.R.; Douglas, S.R.; Dunford, D.

1997-01-01

Simulation of ultrasonic inspection of engineering components have been performed at the Chalk River Laboratories of AECL for over 10 years. The computer model, called EWE for Elastic Wave Equations, solves the Elastic Wave Equations using a novel finite difference scheme. It simulates the propagation of an ultrasonic wave from the transducer to a flaw, the scatter of waves from the flaw, and measurement of signals at a receive transducer. Regions of different materials, water and steel for example, can be simulated. In addition, regions with slightly different material properties from the parent material can be investigated. The two major types of output are displays of the ultrasonic waves inside the component and the corresponding A-scans. EPRI and other organizations have used ultrasonic models for: defining acceptable ultrasonic inspection procedures, designing and evaluating inspection techniques, and for quantifying inspection reliability. The EWE model has been applied to the inspection of large pipes in a nuclear plant, gas pipeline welds and steam generator tubes. Most recent work has dealt with the ultrasonic inspection of pressure tubes in CANDU reactors. Pressure tube inspections can reliably detect and size defects; however, there are improvements that can be made. For example, knowing the sharpness of a flaw-tip is crucial for fitness for service assessments. Computer modelling of the ultrasonic inspection of flaws with different root radius has suggested inspection techniques that provide flaw tip radius information. A preliminary investigation of these methods has been made in the laboratory. The basis for the model will be reviewed at the presentation. Then the results of computer simulations will be displayed on a PC using an interactive program that analyzes simulated A-scans. This software tool gives inspection staff direct access to the results of computer simulations. (author)

Comparison of API 510 pressure vessels inspection planning with API 581 risk-based inspection planning approaches

International Nuclear Information System (INIS)

Shishesaz, Mohammad Reza; Nazarnezhad Bajestani, Mohammad; Hashemi, Seyed Javad; Shekari, Elahe

2013-01-01

To ensure mechanical integrity, all pressure vessels shall be inspected at the intervals provided in inspection codes or based on a risk-based inspection (RBI) assessment. The RBI assessment may allow previously established inspection intervals to be extended. This paper describes the methodology, analysis and results of two RBI studies conducted on 293 pressure vessel components in two crude oil distillation units. Based on API RBI methodology in API 581 (2008), risk target concept was used for determining inspection dates. It was shown that when thinning is the major active damage, the RBI recommended intervals are as long as twice the API 510 intervals. This paper summarizes that, as a fundamental step in the risk calculation, RBI has a more defined methodology for evaluating equipment for multiple damage mechanisms and a more defined approach to specify the use of other inspection technologies beyond the traditional visual, ultrasonic, and radiography tests. -- Highlights: • RBI calculated inspection intervals are as long as twice of API 510 inspection code. • Two case studies verified the advantage of RBI in inspection planning. • RBI is a more reliable methodology when evaluating multiple damage mechanisms. • Damage factor calculations can be used for determining RSFa value in FFS assessments

Pump failure leads to alternative vertical pump condition monitoring technique

International Nuclear Information System (INIS)

DeVilliers, Adriaan; Glandon, Kevin

2011-01-01

Condition monitoring and detecting early signs of potential failure mechanisms present particular problems in vertical pumps. Most often, the majority of the pump assembly is not readily accessible for visual or audible inspection or conventional vibration monitoring techniques using accelerometers and/or proximity sensors. The root cause failure analysis of a 2-stage vertical centrifugal service-water pump at a nuclear power generating facility in the USA is presented, highlighting this long standing challenge in condition monitoring of vertical pumps. This paper will summarize the major findings of the root cause analysis (RCA), highlight the limitations of traditional monitoring techniques, and present an expanded application of motor current monitoring as a means to gain insight into the mechanical performance and condition of a pump. The 'real-world' example of failure, monitoring and correlation of the monitoring technique to a detailed pump disassembly inspection is also presented. This paper will explain some of the reasons behind well known design principles requiring natural frequency separation from known forcing frequencies, as well as explore an unexpected submerged brittle fracture failure mechanism, and how such issues may be avoided. (author)

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 applied for OWT....... With the integration of CMI by means Bayesian inference, a slightly change of first inspection times are coming up, influenced by the reduction of the uncertainty and harsher or milder external agents....

Automated in-core image generation from video to aid visual inspection of nuclear power plant cores

Energy Technology Data Exchange (ETDEWEB)

Murray, Paul, E-mail: paul.murray@strath.ac.uk [Department of Electronic and Electrical Engineering, University of Strathclyde, Technology and Innovation Centre, 99 George Street, Glasgow, G1 1RD (United Kingdom); West, Graeme; Marshall, Stephen; McArthur, Stephen [Dept. Electronic and Electrical Engineering, University of Strathclyde, Royal College Building, 204 George Street, Glasgow G1 1XW (United Kingdom)

2016-04-15

Highlights: • A method is presented which improves visual inspection of reactor cores. • Significant time savings are made to activities on the critical outage path. • New information is extracted from existing data sources without additional overhead. • Examples from industrial case studies across the UK fleet of AGR stations. - Abstract: Inspection and monitoring of key components of nuclear power plant reactors is an essential activity for understanding the current health of the power plant and ensuring that they continue to remain safe to operate. As the power plants age, and the components degrade from their initial start-of-life conditions, the requirement for more and more detailed inspection and monitoring information increases. Deployment of new monitoring and inspection equipment on existing operational plant is complex and expensive, as the effect of introducing new sensing and imaging equipment to the existing operational functions needs to be fully understood. Where existing sources of data can be leveraged, the need for new equipment development and installation can be offset by the development of advanced data processing techniques. This paper introduces a novel technique for creating full 360° panoramic images of the inside surface of fuel channels from in-core inspection footage. Through the development of this technique, a number of technical challenges associated with the constraints of using existing equipment have been addressed. These include: the inability to calibrate the camera specifically for image stitching; dealing with additional data not relevant to the panorama construction; dealing with noisy images; and generalising the approach to work with two different capture devices deployed at seven different Advanced Gas Cooled Reactor nuclear power plants. The resulting data processing system is currently under formal assessment with a view to replacing the existing manual assembly of in-core defect montages. Deployment of the

Pipe inspection using the BTX-II. Innovative technology summary report

International Nuclear Information System (INIS)

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

Pipe inspection using the pipe crawler. Innovative technology summary report

International Nuclear Information System (INIS)

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

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.

Pipe inspection using the BTX-II. 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.

Path Planning & Measurement Registration for Robotic Structural Asset Monitoring

OpenAIRE

Pierce , Stephen Gareth; Macleod , Charles Norman; Dobie , Gordon; Summan , Rahul

2014-01-01

International audience; The move to increased levels of autonomy for robotic delivery of inspection for asset monitoring, demands a structured approach to path planning and measurement data presentation that greatly surpasses the more ad‐,hoc approach typically employed by remotely controlled, but manually driven robotic inspection vehicles. The authors describe a traditional CAD/CAM approach to motion planning (as used in machine tool operation) which has numerous benefits including the...

Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

Energy Technology Data Exchange (ETDEWEB)

Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

1993-12-01

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 67 of the reports issued on these in-depth team inspections were 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 systems, structures, and components. Relevant information was extracted from these inspection reports and 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. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

OSE inspection of computer security: Review

International Nuclear Information System (INIS)

Jaehne, E.M.

1987-01-01

The inspection process within the Department of Energy (DOE) serves the function of analyzing and reporting on the performance of security measures and controls in specific areas at sites throughout DOE. Three aspects of this process are discussed based on experience in computer security: Policy basis of performance inspections; Role and form of standards and criteria in inspections; and Conducting an inspection using the standards and criteria. Inspections are based on DOE and other applicable policy in each area. These policy statements have a compliance orientation in which the paper trail is often more clearly discernible than the security intention. The relationship of policy to performance inspections is discussed. To facilitate bridging the gap between the paper trail and the security intention defined by policy, standards and criteria were developed in each area. The consensus process and structure of the resulting product for computer security are discussed. Standards and criteria are inspection tools that support the site in preparing for an inspection and the inspector in conducting one. They form a systematic approach that facilitates consistency in the analysis and reporting of inspection results. Experience using the computer security standards and criteria is discussed

Conceptual design and assessment of in-service inspection and maintenance of KALIMER

Energy Technology Data Exchange (ETDEWEB)

Joo, Young Sang; Kim, Seok Hun; Kim, Jong Bum; Lee, Jae Han [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-05-01

In the conceptual design stage of KALIMER, the philosophy and methodology of in-service inspection (ISI) and maintenance for the reactor system and components are proposed and described. The ISI and maintenance should be carried out throughout plant life to ensure the structural integrity and safety of KALIMER. The conceptual design of ISI and maintenance are performed for considering the design characteristics of KALIMER and the intents of the ASME XI Division 3. This report describes and summarizes the requirements and available methods of ISI and maintenance. The visual inspection and continuous monitoring play a great role in the in-service inspection of KALIMER. The major structures of KALIMER reactor system are designed for maintenance free operation for the plant life time and the maintenance philosophy is to replace major components rather than repair them. The assessment of the ISI accessibility and maintainability is performed and reviewed each major component. The postulated failure defects for each component are estimated and evaluated for KALIMER safety and reliability. 8 refs., 16 figs., 13 tabs. (Author)

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.

Intelligent Belt Conveyor Monitoring and Control

NARCIS (Netherlands)

Pang, Y.

2010-01-01

Belt conveyors have been used worldwide in continuous material transport for about 250 years. Traditional inspection and monitoring of large-scale belt conveyors focus on individual critical components and response to catastrophic system failures. To prevent operational problems caused by the lack

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.

10 CFR 21.41 - Inspections.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Inspections. 21.41 Section 21.41 Energy NUCLEAR REGULATORY COMMISSION REPORTING OF DEFECTS AND NONCOMPLIANCE Inspections, Records § 21.41 Inspections. Each individual, corporation, partnership, dedicating entity, or other entity subject to the regulations in this part shall...

Design considerations, tooling and equipment for remote in-service inspection of radioactive piping and pressure vessel systems

International Nuclear Information System (INIS)

Schmoker, D.S.; Swannack, D.L.

1983-01-01

In-Service Inspection programs are performed to monitor and verify the integrity of a nuclear power plant's primary pressure boundaries. Early detection of abnormal structural or material degradation could preclude serious damage to plant systems. This paper summarizes results obtained in use of remotely-operated nondestructive testing (NDT) equipment for inspection of reactor system components. Experience obtained in operating the Fast Flux Test Facility (FFTF) has provided a basis for field verification of remote NDT equipment designs and has suggested development improvements. Remote Viewing and data gathering systems used include periscopes, borescopes, fiberscopes, hybrid borescopes/fiberscopes, and closed circuit television. A summary of design consideration for inspection equipment and power plant design is presented to achieve improved equipment operation and reduction of plant maintenance downtime

Northeast Inspection Services, Inc. boresonic inspection system evaluation

International Nuclear Information System (INIS)

Nottingham, L.D.; Sabourin, P.F.; Presson, J.H.

1993-04-01

Turbine rotor reliability and remaining life assessment are continuing concerns to electric utilities. Over the years, boresonic inspection and evaluation have served as primary components in rotor remaining life assessment. Beginning with an evaluation of TREES by EPRI in 1982, a series of reports that document the detection and sizing capabilities of several boresonic systems have been made available. These studies should provide utilities with a better understanding of system performance and lead to improved reliability when predicting rotor remaining life. In 1990, the procedures followed for evaluating rotor boresonic performance capabilities were changed to transfer a greater portion of the data analysis function to the participating vendor. This change from previous policy was instituted so that the evaluation results would better reflect the ''final answer'' that a vendor would provide in a real rotor inspection and also to reduce the cost of an evaluation. Among the first vendors to participate in the new performance demonstration was Northeast Inspection Services, Inc. (NISI). The tests reported herein were conducted by NISI personnel under the guidelines of the new plan. Details of the new evaluation plan are also presented. Rotor bore blocks containing surface-connected fatigue cracks, embedded glass beads, and embedded radial-axial oriented disks were used in the evaluation. Data were collected during twenty-five independent passes through the blocks. The evaluation consisted of statistical characterization of the detection capabilities, flaw sizing and location accuracy, and repeatability of the inspection system. The results of the evaluation are included in this report

Computerized automated remote inspection system

International Nuclear Information System (INIS)

The automated inspection system utilizes a computer to control the location of the ultrasonic transducer, the actual inspection process, the display of the data, and the storage of the data on IBM magnetic tape. This automated inspection equipment provides two major advantages. First, it provides a cost savings, because of the reduced inspection time, made possible by the automation of the data acquisition, processing, and storage equipment. This reduced inspection time is also made possible by a computerized data evaluation aid which speeds data interpretation. In addition, the computer control of the transducer location drive allows the exact duplication of a previously located position or flaw. The second major advantage is that the use of automated inspection equipment also allows a higher-quality inspection, because of the automated data acquisition, processing, and storage. This storage of data, in accurate digital form on IBM magnetic tape, for example, facilitates retrieval for comparison with previous inspection data. The equipment provides a multiplicity of scan data which will provide statistical information on any questionable volume or flaw. An automatic alarm for location of all reportable flaws reduces the probability of operator error. This system has the ability to present data on a cathode ray tube as numerical information, a three-dimensional picture, or ''hard-copy'' sheet. One important advantage of this system is the ability to store large amounts of data in compact magnetic tape reels

Automated Inspection of Aircraft

Science.gov (United States)

1998-04-01

This report summarizes the development of a robotic system designed to assist aircraft inspectors by remotely deploying non-destructive inspection (NDI) sensors and acquiring, processing, and storing inspection data. Carnegie Mellon University studie...

AECL experience in fuel channel inspection

Energy Technology Data Exchange (ETDEWEB)

Van Drunen, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Gunn, R. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Mayo, W.R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Scott, D.A. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

1999-06-01

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)

Recurrent safety inspection of German nuclear power plant - performance, schedule and goals. As of 11 August 1995; Periodische Sicherheitsueberpruefung (PSUe) fuer deutsche Kernkraftwerke - Durchfuehrung der PSUe. Vom 11. August 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-23

The recurrent safety inspection is intended as an inspection supplementing the continuous operation monitoring activities within the framework given by the supervisory activities of the supervisory authority. The first recurrent safety inspection is scheduled to be performed about ten years after start-up of the plant, with subsequent inspection intervals to cover ten-year periods, and recorded operating and monitoring results to be taken into account at each recurrent inspection. The purpose of the recurrent safety inspections is to ascertain that post-inspection operation of the plant meets the then required safety standards. Significant testing results of the latest inspection are to be analysed and compared with regard to the current state of the art and operating results accumulated since the previous inspection, for subsequent definition of enhancements if required. (orig./HP) [Deutsch] Die PSUesoll eine Ergaenzung der staendigen Ueberpruefung im Rahmen der atomrechtlichen Aufsicht ueber den Betrieb sein. Eine erstmalige PSUesoll etwa zehn Jahre nach Inbetriebnahme erfolgen. Die weiteren Ueberpruefungen sollen danach jeweils im Abstand von etwa zehn Jahren stattfinden. Die zwischenzeitlichen Erfahrungen aus Betrieb und Aufsicht sind einzubeziehen. Ziel der PSUemuss sein, festzustellen, ob die Anlage auch im Hinblick auf den kuenftigen Betrieb ein ausreichendes Sicherheitsniveau besitzt. Zu diesem Zweck muessen repraesentative Ereignisse dann detailliert untersucht werden, wenn neue Erkenntnisse aus Forschung und Entwicklung sowie aus der Betriebserfahrung seit der letzten Periodischen Sicherheitsueberpruefung dies erfordern. (orig./HP)

Operational inspections

International Nuclear Information System (INIS)

Bystersky, M.

1997-01-01

Special equipment is described, designed for inspection of reactor pressure vessels performed from the inside. Central shaft manipulator ZMM-5 is available for crack detection control using ultrasound and eddy currents, for visual check of surfaces, repair works at the reactor pressure vessel, and hardness measurements. The manipulator consists of the manipulator bridge, a cable container, shaft segments, a control mechanism and auxiliary parts. Eight inspections were performed at the Bohunice nuclear power plant and two at the Paks nuclear power plant. (M.D.)

Experience on inspection at PFPF

International Nuclear Information System (INIS)

Aoki, I.; Yamamoto, Y.; Takahashi, Saburo; Ooshima, Hirofumi; Kuniyasu, Kazufusa.

1993-01-01

In order to reduce a personal radiation exposure, Plutonium Fuel Production Facility (PFPF) introduced an automated MOX fabrication technology. Safeguards system for the PFPF was designed and installed so as to be compatible with automated process operation as much as possible. Introduction of these system in PFPF made possible to do the inspection measurements with unattended mode and Near Real Time Material Accountancy (NRTA), consequently inspection has been carrying out effectively and efficiently. This paper describes the new Inspection activities as a comparison with old Inspection activities based on our experience. (author)

7 CFR 927.60 - Inspection and certification.

Science.gov (United States)

2010-01-01

... WASHINGTON Order Regulating Handling Inspection § 927.60 Inspection and certification. (a) Handlers shall ship only fresh pears inspected by the Federal-State Inspection Service or under a program developed by... 7 Agriculture 8 2010-01-01 2010-01-01 false Inspection and certification. 927.60 Section 927.60...

ROBOTIC TANK INSPECTION END EFFECTOR

International Nuclear Information System (INIS)

Rachel Landry

1999-01-01

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 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

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

Design and implementation of visual inspection system handed in tokamak flexible in-vessel robot

International Nuclear Information System (INIS)

Wang, Hesheng; Xu, Lifei; Chen, Weidong

2016-01-01

In-vessel viewing system (IVVS) is a fundamental tool among the remote handling systems for ITER, which is used to providing information on the status of the in-vessel components. The basic functional requirement of in-vessel visual inspection system is to perform a fast intervention with adequate optical resolution. In this paper, we present the software and hardware solution, which is designed and implemented for tokamak in-vessel viewing system that installed on end-effector of flexible in-vessel robot working under vacuum and high temperature. The characteristic of our in-vessel viewing system consists of two parts: binocular heterogeneous vision inspection tool and first wall scene emersion based augment virtuality. The former protected with water-cooled shield is designed to satisfy the basic functional requirement of visual inspection system, which has the capacity of large field of view and high-resolution for detection precision. The latter, achieved by overlaying first wall tiles images onto virtual first wall scene model in 3D virtual reality simulation system, is designed for convenient, intuitive and realistic-looking visual inspection instead of viewing the status of first wall only by real-time monitoring or off-line images sequences. We present the modular division of system, each of them in smaller detail, and go through some of the design choices according to requirements of in-vessel visual inspection task.

Design and implementation of visual inspection system handed in tokamak flexible in-vessel robot

Energy Technology Data Exchange (ETDEWEB)

Wang, Hesheng; Xu, Lifei [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation, Shanghai Jiao Tong University, Shanghai 200240 (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China)

2016-05-15

In-vessel viewing system (IVVS) is a fundamental tool among the remote handling systems for ITER, which is used to providing information on the status of the in-vessel components. The basic functional requirement of in-vessel visual inspection system is to perform a fast intervention with adequate optical resolution. In this paper, we present the software and hardware solution, which is designed and implemented for tokamak in-vessel viewing system that installed on end-effector of flexible in-vessel robot working under vacuum and high temperature. The characteristic of our in-vessel viewing system consists of two parts: binocular heterogeneous vision inspection tool and first wall scene emersion based augment virtuality. The former protected with water-cooled shield is designed to satisfy the basic functional requirement of visual inspection system, which has the capacity of large field of view and high-resolution for detection precision. The latter, achieved by overlaying first wall tiles images onto virtual first wall scene model in 3D virtual reality simulation system, is designed for convenient, intuitive and realistic-looking visual inspection instead of viewing the status of first wall only by real-time monitoring or off-line images sequences. We present the modular division of system, each of them in smaller detail, and go through some of the design choices according to requirements of in-vessel visual inspection task.

Under-Sodium Inspection Techniques for Reactor Internals of KALIMER-600 using Ultrasonic Waveguide Sensor

International Nuclear Information System (INIS)

Joo, Young Sang; Kim, Seok Hoon; Lee, Jae Han

2005-01-01

KALIMER-600 is a pool type liquid metal reactor (LMR) which is operated with a sodium coolant. The reactor internals of KALIMER-600 are submerged in a liquid sodium pool. As the liquid sodium is opaque to the light, a conventional visual inspection can not be used for observing the internal structures under a sodium condition. An under-sodium viewing (USV) technique using an ultrasonic wave should be applied for the observation of the refueling maneuver and the in-service inspection of the reactor internals. Under-sodium inspection technology utilizing ultrasonic waves has been widely developed for a visualization of the reactor core and internal components of LMR. Immersion sensors and waveguide sensors have been applied to the USV inspection. The immersion sensor has a precise imaging capability, but may have high temperature restrictions and an uncertain life. The waveguide sensor has the advantages of simplicity and reliability, but limited in its movement. The new plate-type waveguide sensor has been developed as a useful alternative to immersion sensors for USV applications. In the viewing and monitoring applications, a beam steering function of a waveguide sensor might be required. A new waveguide sensor and technique are being developed to overcome the limitations of a waveguide ultrasonic sensor. In this study, the under-sodium inspection techniques using the newly developed waveguide sensor for the reactor internal structures of KALIMER-600 is proposed

Wastewater treatment plant inspection program, fiscal year 2006 and 2007 data report

OpenAIRE

Greco, Stacie

2008-01-01

This data report includes the results from Alachua County Environmental Protection Department’s inspections of wastewater treatment plants (WWTP) within Alachua County during the 2006 and 2007 fiscal years (October 2005 – September 2007). Groundwater monitoring data provided to the Florida Department of Environmental Protection Department by the WWTP operators is included for those treatment plants that are required to submit this information (PDF has 44 pages.)

The development of web monitoring digital area monitor

International Nuclear Information System (INIS)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su

2005-01-01

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system

The development of web monitoring digital area monitor

Energy Technology Data Exchange (ETDEWEB)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su [Iljin Radiation Engineering Co., Seoul (Korea, Republic of)

2005-11-15

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system.

How to share inspection practices internationally?

International Nuclear Information System (INIS)

Zerger, B.

2009-01-01

ASN strives to share practices with its foreign counterparts in order to develop and adopt best practice worldwide. With regard to inspection practices, the exchanges are made with AEN, in particular within the context of the Working Group on Inspection Practices (WGIP). As well as being very rewarding, the exchanges sometimes come up against marked differences in terms of inspection organisation and even in the meaning given to the inspections. The WGIP endeavors, however, to make inspection practice recommendations that are as functional and feasible as possible. (author)

Towards formalization of inspection using petrinets

International Nuclear Information System (INIS)

Javed, M.; Naeem, M.; Bahadur, F.; Wahab, A.

2014-01-01

Achieving better quality software has always been a challenge for software developers. Inspection is one of the most efficient techniques, which ensure the quality of software during its development. To the best of our knowledge, current inspection techniques are not realized by any formal approach. In this paper, we propose an inspection technique, which is not only backed by the formal mathematical semantics of Petri nets, but also supports inspecting concurrent processes. We also use a case study of an agent based distributed processing system to demonstrate the inspection of concurrent processes. (author)

Ultrasonic inspection of inpile tubes

International Nuclear Information System (INIS)

Boyd, D.M.; Bossi, H.

1985-01-01

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

System Enhancements for Mechanical Inspection Processes

Science.gov (United States)

Hawkins, Myers IV

2011-01-01

Quality inspection of parts is a major component to any project that requires hardware implementation. Keeping track of all of the inspection jobs is essential to having a smooth running process. By using HTML, the programming language ColdFusion, and the MySQL database, I created a web-based job management system for the 170 Mechanical Inspection Group that will replace the Microsoft Access based management system. This will improve the ways inspectors and the people awaiting inspection view and keep track of hardware as it is in the inspection process. In the end, the management system should be able to insert jobs into a queue, place jobs in and out of a bonded state, pre-release bonded jobs, and close out inspection jobs.

Optimising import phytosanitary inspection

NARCIS (Netherlands)

Surkov, I.

2007-01-01

Keywords: quarantine pest, plant health policy, optimization, import phytosanitary inspection, ‘reduced checks’, optimal allocation of resources, multinomial logistic regression, the Netherlands World trade is a major vector of spread of quarantine plant pests. Border phytosanitary inspection

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

International Nuclear Information System (INIS)

Moore, F.W.

1987-01-01

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

Magnetic particle inspection

Science.gov (United States)

Sastri, Sankar

1990-01-01

The purpose of this experiment is to familiarize the student with magnetic particle inspection and relate it to classification of various defects. Magnetic particle inspection is a method of detecting the presence of cracks, laps, tears, inclusions, and similar discontinuities in ferromagnetic materials such as iron and steel. This method will most clearly show defects that are perpendicular to the magnetic field. The Magnaglo method uses a liquid which is sprayed on the workpiece to be inspected, and the part is magnetized at the same time. The workpiece is then viewed under a black light, and the presence of discontinuity is shown by the formation of a bright indication formed by the magnetic particles over the discontinuity. The equipment and experimental procedures are described.

The use of condition monitoring information for maintenance planning and decision-making

Energy Technology Data Exchange (ETDEWEB)

Laakso, K.; Rosqvist, T. [VTT Industrial Systems (Finland); Paulsen, J.L. [Risoe National Lab., Roskilde (Denmark)

2002-12-01

A survey is presented outlining the use of condition monitoring information in three Nordic nuclear power plants. The questions of the survey relate to the role of condition monitoring in strategic, as well as operative, maintenance planning and decision-making. The survey indicates that condition monitoring is increasingly implemented at nuclear power plants, but very selectively and in a rather slow pace for predictive maintenance. A combined strategy of condition based maintenance and predetermined preventive maintenance is applied for important equipment such as main circulation pumps and steam turbines. A realistic aim is to reduce the number of costly or error prone maintenance and disassembling inspection activities by condition monitoring given that the approach enables a good diagnosis and prediction. Systematic follow-up and analysis of such condition monitoring information followed by a case-specific planning and decision making of timely and rightly directed maintenance actions can justify an extension of the intervals of a number of predetermined inspection, maintenance or periodic testing tasks. (au)

Ultrasonic inspections of fuel alignment pins

International Nuclear Information System (INIS)

Rathgeb, W.; Schmid, R.

1994-01-01

As a remedy to the practical problem of defects in fuel alignment pins made of Inconel X750, an inspection technique has been developed which fully meets the requirements of detecting defects. The newly used fuel alignment pins made of austenite are easy to test and therefore satisfy the necessity of further inspections.For the fuel alignment pins of the upper core structure a safe and fast inspection technique was made available. The inspection sensitivity is high and it is possible to give quantitative directions concerning defect orientation and depth. After the required inspections had been concluded in 1989, a total of 18 inspections were carried out in various national and international nuclear power plants in the following years. During this time more than 6000 fuel alignment pines were examined.For the fuel alignment pins the inspection technique provided could increase the understanding of the defect process. This technique contributed to the development of an adaptive and economical repair strategy. ((orig.))

PWR vessel inspection performance improvements

International Nuclear Information System (INIS)

Blair Fairbrother, D.; Bodson, Francis

1998-01-01

A compact robot for ultrasonic inspection of reactor vessels has been developed that reduces setup logistics and schedule time for mandatory code inspections. Rather than installing a large structure to access the entire weld inspection area from its flange attachment, the compact robot examines welds in overlapping patches from a suction cup anchor to the shell wall. The compact robot size allows two robots to be operated in the vessel simultaneously. This significantly reduces the time required to complete the inspection. Experience to date indicates that time for vessel examinations can be reduced to fewer than four days. (author)

Employing innovative techniques to reduce inspection times

International Nuclear Information System (INIS)

Heumueller, R.; Guse, G.; Dirauf, F.; Fischer, E.

1997-01-01

Shorter inspection periods mean lower revision costs and less tight revision schedules, but must not detract from the quality of inspection findings. This requirement imposes upon the company performing the inspection the need for top achievements both in quality management and in the use of innovative techniques. Flexible equipment systems and inspection techniques adapted to specific purposes are able to reduce inspection times in many inspection jobs. As part of a complete system designed to reduce inspection times, the new Saphir (Siemens Alok Phased Array Integrated Reliable UT-System) inspection equipment system is the core of most of the recent innovations. Being an integrated inspection equipment system, it is able to handle conventional US probes as well as arrays and phased arrays. It is open for further matching to specific inspection and administrative requirements and developments, and it may be incorporated in the network of an integrated system with a database. A technological leap in probe design in the past few years has allowed controllable wave fields to be generated which are in no way inferior to those of conventional probes with fixed angles of incidence. In this way, a number of inspection techniques can be implemented with a single probe. This reduces inspection times, setup and retooling times, and doses. Typical examples already used in practice are the LLT (longitudinal-longitudinal-transverse waves) technique and the integration of inspections for longitudinal and transverse defects in a single run. In the near future, surfaces with complicated curvatures will be inspected by novel modular robot systems consisting of individual modules of linear axes and rotational axes. (orig.) [de

Automated PCB Inspection System

Directory of Open Access Journals (Sweden)

Syed Usama BUKHARI

2017-05-01

Full Text Available Development of an automated PCB inspection system as per the need of industry is a challenging task. In this paper a case study is presented, to exhibit, a proposed system for an immigration process of a manual PCB inspection system to an automated PCB inspection system, with a minimal intervention on the existing production flow, for a leading automotive manufacturing company. A detailed design of the system, based on computer vision followed by testing and analysis was proposed, in order to aid the manufacturer in the process of automation.

A condition-based maintenance policy with non-periodic inspections for a two-unit series system

International Nuclear Information System (INIS)

Castanier, B.; Grall, A.; Berenguer, C.

2005-01-01

This paper considers a condition-based maintenance policy for a two-unit deteriorating system. Each unit is subject to gradual deterioration and is monitored by sequential non-periodic inspections. It can be maintained by good as new preventive or corrective replacements. Every inspection or replacement entails a set-up cost and a component-specific unit cost but if actions on the two components are combined, the set-up cost is charged only once. A parametric maintenance decision framework is proposed to coordinate inspection/replacement of the two components and minimize the long-run maintenance cost of the system. A stochastic model is developed on the basis of the semi-regenerative properties of the maintained system state and the associated cost model is used to assess and optimize the performance of the maintenance model. Numerical experiments emphasize the interest of a control of the operation groupings

Multifrequency Eddy Current Inspection of Corrosion in Clad Aluminum Riveted Lap Joints and Its Effect on Fatigue Life

Science.gov (United States)

Okafor, A. C.; Natarajan, S.

2007-03-01

Aging aircraft are prone to corrosion damage and fatigue cracks in riveted lap joints of fuselage skin panels. This can cause catastrophic failure if not detected and repaired. Hence detection of corrosion damage and monitoring its effect on structural integrity are essential. This paper presents multifrequency eddy current (EC) inspection of corrosion damage and machined material loss defect in clad A1 2024-T3 riveted lap joints and its effect on fatigue life. Results of eddy current inspection, corrosion product removal and fatigue testing are presented.

Multifrequency Eddy Current Inspection of Corrosion in Clad Aluminum Riveted Lap Joints and Its Effect on Fatigue Life

International Nuclear Information System (INIS)

Okafor, A. C.; Natarajan, S.

2007-01-01

Aging aircraft are prone to corrosion damage and fatigue cracks in riveted lap joints of fuselage skin panels. This can cause catastrophic failure if not detected and repaired. Hence detection of corrosion damage and monitoring its effect on structural integrity are essential. This paper presents multifrequency eddy current (EC) inspection of corrosion damage and machined material loss defect in clad A1 2024-T3 riveted lap joints and its effect on fatigue life. Results of eddy current inspection, corrosion product removal and fatigue testing are presented

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…

Evaluating Heuristics for Planning Effective and Efficient Inspections

Science.gov (United States)

Shull, Forrest J.; Seaman, Carolyn B.; Diep, Madeline M.; Feldmann, Raimund L.; Godfrey, Sara H.; Regardie, Myrna

2010-01-01

A significant body of knowledge concerning software inspection practice indicates that the value of inspections varies widely both within and across organizations. Inspection effectiveness and efficiency can be measured in numerous ways, and may be affected by a variety of factors such as Inspection planning, the type of software, the developing organization, and many others. In the early 1990's, NASA formulated heuristics for inspection planning based on best practices and early NASA inspection data. Over the intervening years, the body of data from NASA inspections has grown. This paper describes a multi-faceted exploratory analysis performed on this · data to elicit lessons learned in general about conducting inspections and to recommend improvements to the existing heuristics. The contributions of our results include support for modifying some of the original inspection heuristics (e.g. Increasing the recommended page rate), evidence that Inspection planners must choose between efficiency and effectiveness, as a good tradeoff between them may not exist, and Identification of small subsets of inspections for which new inspection heuristics are needed. Most Importantly, this work illustrates the value of collecting rich data on software Inspections, and using it to gain insight into, and Improve, inspection practice.

Policy implications of Iran's Nuclear Deal in technical terms for the plutonium route, uranium route, covert options, inspections, monitoring and verifications

International Nuclear Information System (INIS)

Pinheiro, Andre Ricardo M.

2017-01-01

The present Paper addresses the policy implications of Joint Comprehensive Plan of Action (JCPOA) known as 'Ian Nuclear Deal', implemented on 16 th January of 2016 between the Iran and the P5+1 countries (the U.S., U.K. France, Germany, Russia, and China), along with the EU in technical terms to analyze the Plutonium Route, Uranium Route and the Covert options and Inspections, Monitoring and Verifications. A historical review is presented to understand how the Iranian Nuclear Program is formed. Following is shown the current nuclear facilities in Iran and its capacity to process nuclear materials. It is analyzed the impact of JCPOA in Uranium and Plutonium routes. Covert Options always will be an option, so the most sensitive impact is related to the new monitoring and verification policies that must ensure real control of illegal procedures. The main conclusion is that the deal postpones the Iran's nuclear program for more than a decade (15 years), delaying Iran's nuclear bomb time from a few months to at least one year, although there is a current latent capacity to develop a nuclear bomb in Uranium route. It also gives IAEA inspectors capability to monitor nuclear activities and prevent to possible development to a nuclear bomb. To arrive in this conclusion an extensive technical analyze of impact of JCPOA in Iran's nuclear capabilities was made to discover how effective is the deal to prevent Iran to build, or acquire a nuclear weapon. (author)

Policy implications of Iran's Nuclear Deal in technical terms for the plutonium route, uranium route, covert options, inspections, monitoring and verifications

Energy Technology Data Exchange (ETDEWEB)

Pinheiro, Andre Ricardo M., E-mail: andrericardopinheiro@usp.br [Universidade de São Paulo (USP), SP (Brazil). Departamento de Engenharia Naval; Guimarães, Leonam dos Santos, E-mail: leonam@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2017-07-01

The present Paper addresses the policy implications of Joint Comprehensive Plan of Action (JCPOA) known as 'Ian Nuclear Deal', implemented on 16{sup th} January of 2016 between the Iran and the P5+1 countries (the U.S., U.K. France, Germany, Russia, and China), along with the EU in technical terms to analyze the Plutonium Route, Uranium Route and the Covert options and Inspections, Monitoring and Verifications. A historical review is presented to understand how the Iranian Nuclear Program is formed. Following is shown the current nuclear facilities in Iran and its capacity to process nuclear materials. It is analyzed the impact of JCPOA in Uranium and Plutonium routes. Covert Options always will be an option, so the most sensitive impact is related to the new monitoring and verification policies that must ensure real control of illegal procedures. The main conclusion is that the deal postpones the Iran's nuclear program for more than a decade (15 years), delaying Iran's nuclear bomb time from a few months to at least one year, although there is a current latent capacity to develop a nuclear bomb in Uranium route. It also gives IAEA inspectors capability to monitor nuclear activities and prevent to possible development to a nuclear bomb. To arrive in this conclusion an extensive technical analyze of impact of JCPOA in Iran's nuclear capabilities was made to discover how effective is the deal to prevent Iran to build, or acquire a nuclear weapon. (author)

INSPECT: a package of computer programs for planning and evaluating safeguards inspections

International Nuclear Information System (INIS)

Mullen, M.F.

1980-01-01

As part of the US Program of Technical Assistance to IAEA Safeguards, PNL has developed a package of computer programs, called INSPECT, that can be used in planning and evaluating safeguards inspections of various types of nuclear facilities. The programs are based on the statistical methods described in Part F of the IAEA Safeguards Technical Manual and can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, and a measure of the effectiveness of the inspection plan. The paper describes the programs, reviews a number of applications, and indicates areas for future work

Automated optics inspection analysis for NIF

International Nuclear Information System (INIS)

Kegelmeyer, Laura M.; Clark, Raelyn; Leach, Richard R.; McGuigan, David; Kamm, Victoria Miller; Potter, Daniel; Salmon, J. Thad; Senecal, Joshua; Conder, Alan; Nostrand, Mike; Whitman, Pamela K.

2012-01-01

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.

Automated optics inspection analysis for NIF

Energy Technology Data Exchange (ETDEWEB)

Kegelmeyer, Laura M., E-mail: kegelmeyer1@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA (United States); Clark, Raelyn; Leach, Richard R.; McGuigan, David; Kamm, Victoria Miller; Potter, Daniel; Salmon, J. Thad; Senecal, Joshua; Conder, Alan; Nostrand, Mike; Whitman, Pamela K. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

2012-12-15

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.

Reliability-Based Inspection Planning for Structural Systems

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard

1993-01-01

A general model for reliability-based optimal inspection and repair strategies for structural systems is described. The total expected costs in the design lifetime is minimized with the number of inspections, the inspection times and efforts as decision variables. The equivalence of this model...... with a preposterior analysis from statistical decision theory is discussed. It is described how information obtained by an inspection can be used in a repair decision. Stochastic models for inspection, measurement and repair actions are presented. The general model is applied for inspection and repair planning...

New Swedish regulations in the area of plant inspection and in-service inspection

International Nuclear Information System (INIS)

Hansson, B.

1998-01-01

History and present status od Swedish regulations in the field of NPP inspection and in-service inspection are described. The presentation focuses on the development of regulations and establishing new ones. A description of different organisations involved is included

9 CFR 381.67 - Young chicken and squab slaughter inspection rate maximums under traditional inspection procedure.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Young chicken and squab slaughter... INSPECTION REGULATIONS Operating Procedures § 381.67 Young chicken and squab slaughter inspection rate... inspector per minute under the traditional inspection procedure for the different young chicken and squab...

7 CFR 57.925 - Inspection of imported eggs.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Inspection of imported eggs. 57.925 Section 57.925... AGRICULTURAL MARKETING ACT OF 1946 AND THE EGG PRODUCTS INSPECTION ACT (CONTINUED) INSPECTION OF EGGS (EGG PRODUCTS INSPECTION ACT) Regulations Governing the Inspection of Eggs Imports § 57.925 Inspection of...

46 CFR 107.211 - Original Certificate of Inspection.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Original Certificate of Inspection. 107.211 Section 107... INSPECTION AND CERTIFICATION Inspection and Certification § 107.211 Original Certificate of Inspection. (a) The owner or builder of a unit applies for an inspection for an original Certificate of Inspection by...

9 CFR 381.309 - Finished product inspection.

Science.gov (United States)

2010-01-01

... Section 381.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned Products § 381.309...

Inspection system performance test procedure

International Nuclear Information System (INIS)

Jensen, C.E.

1995-01-01

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

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)

Inspections - a cost effective approach

International Nuclear Information System (INIS)

Joseph, C.

1981-01-01

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

Can non-destructive inspection be reliable

International Nuclear Information System (INIS)

Silk, M.G.; Stoneham, A.M.; Temple, J.A.G.

1988-01-01

The paper on inspection is based on the book ''The reliability of non-destructive inspection: assessing the assessment of structures under stress'' by the present authors (published by Adam Hilger 1987). Emphasis is placed on the reliability of inspection and whether cracks in welds or flaws in components can be detected. The need for non-destructive testing and the historical attitudes to non-destructive testing are outlined, along with the case of failure. Factors influencing reliable inspection are discussed, and defect detection trials involving round robin tests are described. The development of reliable inspection techniques and the costs of reliability and unreliability are also examined. (U.K.)

Development of radioactive materials inspection system

International Nuclear Information System (INIS)

Yang Lu; Wang Guobao; Chen Yuhua; Li Latu; Zhang Sujing

2005-01-01

Radioactive materials inspection system which is applied to inspect the horror activities of radioactive materials and its illegal transfer. The detector sections are made of highly stable and credible material. It has high sensitivity to radioactive materials. The inspect lowest limit of inspection is the 2-3 times to the background, the energy range is 30 keV-2.5 MeV and the response time is 0.5 s. Inspection message can be transmitted through wired or wireless web to implement remote control. The structure of the system is small, light and convenient. It is ideal for protecting society and public from the harm of the radiation. (authors)

Lean Construction Applications for Bridge Inspection

Science.gov (United States)

2017-10-01

Lean philosophy was used to analyze the efficiency of bridge inspection. Emphasis was put on identifying activities that add value to the final output, an owner approved bridge inspection report. 26 bridge inspections were shadowed. Time spent on bri...

9 CFR 318.309 - Finished product inspection.

Science.gov (United States)

2010-01-01

... Section 318.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY... Canning and Canned Products § 318.309 Finished product inspection. (a) Finished product inspections must...

Development of inspection robots for bridge cables.

Science.gov (United States)

Yun, Hae-Bum; Kim, Se-Hoon; Wu, Liuliu; Lee, Jong-Jae

2013-01-01

This paper presents the bridge cable inspection robot developed in Korea. Two types of the cable inspection robots were developed for cable-suspension bridges and cable-stayed bridge. The design of the robot system and performance of the NDT techniques associated with the cable inspection robot are discussed. A review on recent advances in emerging robot-based inspection technologies for bridge cables and current bridge cable inspection methods is also presented.

GRIM : Leveraging GPUs for Kernel integrity monitoring

NARCIS (Netherlands)

Koromilas, Lazaros; Vasiliadis, Giorgos; Athanasopoulos, Ilias; Ioannidis, Sotiris

2016-01-01

Kernel rootkits can exploit an operating system and enable future accessibility and control, despite all recent advances in software protection. A promising defense mechanism against rootkits is Kernel Integrity Monitor (KIM) systems, which inspect the kernel text and data to discover any malicious

Runway Inspection by RPAS

Directory of Open Access Journals (Sweden)

Stanislav Absolon

2015-10-01

Full Text Available This article discusses the use of the RPAS for the inspection of the airport operating areas. The paper compares the current process of the inspection of the airport operating areas by the airport staff with the possibilities which are offered by the use of the modern technology RPAS. The following text also describes how to inspect airport operating areas by the RPAS, specific technical possibilities and the applicable technical solutions. Furthermore there are variants of piloting the RPAS, comparing usable equipment, equipment for video recording and the possibility of using thermal imaging camera in the article.

Non-destructive inservice inspections

International Nuclear Information System (INIS)

Kauppinen, P.; Sarkimo, M.; Lahdenperae, K.

1998-01-01

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)

Capacity of the equipment family SICOM to inspect fuel elements; Capacidad de los equipos familia SICOM para inspeccionar elementos de combustible

Energy Technology Data Exchange (ETDEWEB)

Sanchez Siguero, A.; Sola, A.

2013-07-01

To check the status where the fuel assemblies are after has been operating in the core of nuclear plants, inspections have been conducted to carry out an improvement in the behavior of alloys used in pods of fuel, the control of corrosion of these pods because of heat, reducing the transfer of heat due to the oxide and with the support of visual inspections monitor the physical integrity of the fuel elements.

9 CFR 355.7 - Inauguration of inspection.

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inauguration of inspection. 355.7 Section 355.7 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

Developing the information management system for safeguards national inspection

International Nuclear Information System (INIS)

Park, S. J.; Jeon, I.; Park, W. S.; Min, K. S.

2003-01-01

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

In-service inspection of pressurized water reactors

International Nuclear Information System (INIS)

Rapin, M.; Saglio, R.

1983-01-01

French legislation, which is more demanding than in other countries, had led Electricite de France, the State-owned utility, to acquire better performance in-service inspection facilities than those which existed previously. This fact has spurred the industrial development of the new technical facilities which are used worldwide today. This article presents the ''in-service inspection machine'' (MIS) for the inspection of the welds of a PWR vessel, and the inspection device of steam generator tubes; the MIS allow a remote-viewing, ultrasonic and gamma-graphic inspection; Foucault currents are the only one method adapted to the inspection steam generator tubes [fr

A locomotive inspection robot for turbine building interior inspection in nuclear power plants

International Nuclear Information System (INIS)

Obama, M.; Ozaki, F.; Asano, K.

1985-01-01

A locomotive inspection robot, named Turbine Building Inspection System (TBIS), has been developed for turbine building interior inspections in nuclear power plants. This robot is made up of a vehicle, a telescopic support, turning head and a multijoint arm which has dual TV cameras and a diagnostic rod on its tip. The multijoint arm has 17 degrees of freedom and its length is 243 cm. Minimum and maximum heights for the multijoint arm shoulder are 1.5 meter and 4 meters respectively. The total degree of freedom in the combination of the multijoint arm, turning head and telescopic support is 19 and the area, it is capable of inspecting, is equal to the cylindrical dome whose height and diameter are 6.4 meters and 4.8 meters respectively. The design philosophy, hardware structure and operation method of the TBIS are described. 2 refs.; 10 figs

Wafer plane inspection for advanced reticle defects

Science.gov (United States)

Nagpal, Rajesh; Ghadiali, Firoz; Kim, Jun; Huang, Tracy; Pang, Song

2008-05-01

Readiness of new mask defect inspection technology is one of the key enablers for insertion & transition of the next generation technology from development into production. High volume production in mask shops and wafer fabs demands a reticle inspection system with superior sensitivity complemented by a low false defect rate to ensure fast turnaround of reticle repair and defect disposition (W. Chou et al 2007). Wafer Plane Inspection (WPI) is a novel approach to mask defect inspection, complementing the high resolution inspection capabilities of the TeraScanHR defect inspection system. WPI is accomplished by using the high resolution mask images to construct a physical mask model (D. Pettibone et al 1999). This mask model is then used to create the mask image in the wafer aerial plane. A threshold model is applied to enhance the inspectability of printing defects. WPI can eliminate the mask restrictions imposed on OPC solutions by inspection tool limitations in the past. Historically, minimum image restrictions were required to avoid nuisance inspection stops and/or subsequent loss of sensitivity to defects. WPI has the potential to eliminate these limitations by moving the mask defect inspections to the wafer plane. This paper outlines Wafer Plane Inspection technology, and explores the application of this technology to advanced reticle inspection. A total of twelve representative critical layers were inspected using WPI die-to-die mode. The results from scanning these advanced reticles have shown that applying WPI with a pixel size of 90nm (WPI P90) captures all the defects of interest (DOI) with low false defect detection rates. In validating CD predictions, the delta CDs from WPI are compared against Aerial Imaging Measurement System (AIMS), where a good correlation is established between WPI and AIMSTM.

Development of Inspection Robots for Bridge Cables

Directory of Open Access Journals (Sweden)

Hae-Bum Yun

2013-01-01

Full Text Available This paper presents the bridge cable inspection robot developed in Korea. Two types of the cable inspection robots were developed for cable-suspension bridges and cable-stayed bridge. The design of the robot system and performance of the NDT techniques associated with the cable inspection robot are discussed. A review on recent advances in emerging robot-based inspection technologies for bridge cables and current bridge cable inspection methods is also presented.

Automated Intelligent Monitoring and the Controlling Software System for Solar Panels

OpenAIRE

Nalamvar, Hitesh Sanzhay; Ivanov, Maksim Anatoljevich; Baydali, Sergey Anatolievich

2017-01-01

The inspection of the solar panels on a periodic basis is important to improve longevity and ensure performance of the solar system. To get the most solar potential of the photovoltaic (PV) system is possible through an intelligent monitoring & controlling system. The monitoring & controlling system has rapidly increased its popularity because of its user-friendly graphical interface for data acquisition, monitoring, controlling and measurements. In order to monitor the performance of the sys...

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.

Thermographic inspection of pipes, tanks, and containment liners

Energy Technology Data Exchange (ETDEWEB)

Renshaw, Jeremy B., E-mail: jrenshaw@epri.com; Muthu, Nathan [Electric Power Research Institute, 1300 West WT Harris Blvd., Charlotte, NC 28262 (United States); Lhota, James R.; Shepard, Steven M., E-mail: sshepard@thermalwave.com [Thermal Wave Imaging, 845 Livernois St., Ferndale, MI 48220 (United States)

2015-03-31

Nuclear power plants are required to operate at a high level of safety. Recent industry and license renewal commitments aim to further increase safety by requiring the inspection of components that have not traditionally undergone detailed inspected in the past, such as tanks and liners. NEI 09-14 requires the inspection of buried pipes and tanks while containment liner inspections are required as a part of license renewal commitments. Containment liner inspections must inspect the carbon steel liner for defects - such as corrosion - that could threaten the pressure boundary and ideally, should be able to inspect the surrounding concrete for foreign material that could be in contact with the steel liner and potentially initiate corrosion. Such an inspection requires a simultaneous evaluation of two materials with very different material properties. Rapid, yet detailed, inspection results are required due to the massive size of the tanks and containment liners to be inspected. For this reason, thermal NDE methods were evaluated to inspect tank and containment liner mockups with simulated defects. Thermographic Signal Reconstruction (TSR) was utilized to enhance the images and provide detailed information on the sizes and shapes of the observed defects. The results show that thermographic inspection is highly sensitive to the defects of interest and is capable of rapidly inspecting large areas.

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.

7 CFR 75.21 - Grain sample inspection.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Grain sample inspection. 75.21 Section 75.21... AND CERTIFICATION OF QUALITY OF AGRICULTURAL AND VEGETABLE SEEDS Inspection § 75.21 Grain sample inspection. A sample inspection shall be performed by examining official grain samples received from FGIS to...

7 CFR 868.44 - New original inspection.

Science.gov (United States)

2010-01-01

... 7 Agriculture 7 2010-01-01 2010-01-01 false New original inspection. 868.44 Section 868.44... FOR CERTAIN AGRICULTURAL COMMODITIES Regulations Original Inspection Service § 868.44 New original... applicant may request a new original inspection on any previously inspected lot; except that a new original...

49 CFR 396.13 - Driver inspection.

Science.gov (United States)

2010-10-01

... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS INSPECTION, REPAIR, AND MAINTENANCE § 396.13 Driver inspection. Before driving a motor vehicle, the driver shall: (a) Be satisfied that the motor vehicle is in safe operating condition; (b) Review the last driver vehicle inspection...

In-camera video-stream processing for bandwidth reduction in web inspection

Science.gov (United States)

Jullien, Graham A.; Li, QiuPing; Hajimowlana, S. Hossain; Morvay, J.; Conflitti, D.; Roberts, James W.; Doody, Brian C.

1996-02-01

Automated machine vision systems are now widely used for industrial inspection tasks where video-stream data information is taken in by the camera and then sent out to the inspection system for future processing. In this paper we describe a prototype system for on-line programming of arbitrary real-time video data stream bandwidth reduction algorithms; the output of the camera only contains information that has to be further processed by a host computer. The processing system is built into a DALSA CCD camera and uses a microcontroller interface to download bit-stream data to a XILINXTM FPGA. The FPGA is directly connected to the video data-stream and outputs data to a low bandwidth output bus. The camera communicates to a host computer via an RS-232 link to the microcontroller. Static memory is used to both generate a FIFO interface for buffering defect burst data, and for off-line examination of defect detection data. In addition to providing arbitrary FPGA architectures, the internal program of the microcontroller can also be changed via the host computer and a ROM monitor. This paper describes a prototype system board, mounted inside a DALSA camera, and discusses some of the algorithms currently being implemented for web inspection applications.

Do school inspections improve primary school performance?

OpenAIRE

Dinand Webbink; Rob Luginbuhl; I. de Wolf

2007-01-01

Inspectors from the Dutch Inspectorate of Education inspect primary schools, write inspection reports on each inspected school, and make recommendations as to how each school can improve. We test whether these inspections result in better school performance. Using a fixed-effects model, we find evidence that school inspections do lead to measurably better school performance. Our assessment of school performance is based on the Cito test scores of pupils in their final year of primary school. ...

Magnetic rubber inspection (MRI)

International Nuclear Information System (INIS)

Carro, L.

1997-01-01

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

29 CFR 1960.31 - Inspections by OSHA.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Inspections by OSHA. 1960.31 Section 1960.31 Labor... MATTERS Inspection and Abatement § 1960.31 Inspections by OSHA. (a) The Secretary or the Secretary's... scheduled inspections as an integral part of OSHA's evaluation of an agency's safety and health program in...

Czech interim spent fuel storage facility: operation experience, inspections and future plans

International Nuclear Information System (INIS)

Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

1999-01-01

The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

Inspection method of cable-stayed bridge using magnetic flux leakage detection: principle, sensor design, and signal processing

International Nuclear Information System (INIS)

Xu, Fengyu; Wang, Xingsong; Wu, Hongtao

2012-01-01

A nondestructive testing technique based on magnetic flux leakage is presented to inspect automatically the stay cables with large diameters of a cable-stayed bridge. Using the proposed inspection method, an online nondestructive testing (NDT) modular sensor is developed. The wreath-like sensor is composed of several sensor units that embrace the cable at equal angles. Each sensor unit consists of two permanent magnets and a hall sensor to detect the magnetic flux density. The modular sensor can be installed conveniently on cables with various diameters by increasing the number of sensor units and adjusting the relative distances between adjacent sensor units. Results of the experiments performed on a man-made cable with faults prove that the proposed sensor can inspect the status signals of the inner wires of the cables. To filter the interfering signals, three processing algorithms are discussed, including the moving average method, improved detrending algorithm, and signal processing based on a digital filter. Results show that the developed NDT sensor carried by a cable inspection robot can move along the cable and monitor the state of the stay cables

Container Inspection Utilizing 14 MeV Neutrons

Science.gov (United States)

Valkovic, Vladivoj; Sudac, Davorin; Nad, Karlo; Obhodas, Jasmina

2016-06-01

A proposal for an autonomous and flexible ship container inspection system is presented. This could be accomplished by the incorporation of an inspection system on various container transportation devices (straddle carriers, yard gentry cranes, automated guided vehicles, trailers). The configuration is terminal specific and it should be defined by the container terminal operator. This enables that no part of the port operational area is used for inspection. The inspection scenario includes container transfer from ship to transportation device with the inspection unit mounted on it. The inspection is performed during actual container movement to the container location. A neutron generator without associated alpha particle detection is used. This allows the use of higher neutron intensities (5 × 109 - 1010 n/s in 4π). The inspected container is stationary in the “inspection position” on the transportation device while the “inspection unit” moves along its side. The following analytical methods will be used simultaneously: neutron radiography, X-ray radiography, neutron activation analysis, (n, γ) and (n,n'γ) reactions, neutron absorption. and scattering, X-ray backscattering. The neutron techniques will utilize “smart collimators” for neutrons and gamma rays, both emitted and detected. The inspected voxel is defined by the intersection of the neutron generator and the detectors solid angles. The container inspection protocol is based on identification of discrepancies between the cargo manifest, elemental “fingerprint” and radiography profiles. In addition, the information on container weight is obtained during the container transport and screening by measuring of density of material in the container.

MACS as a tool for international inspections

International Nuclear Information System (INIS)

Curtiss, J.A.; Indusi, J.P.

1995-01-01

General acceptance of the challenge provision in the Chemical Weapons Convention has the potential for influence in other arms control areas. While most applications of the challenge inspection may be straightforward, there may be instances where access to the site by inspectors may be problematic. The MACS system described in this paper was developed to respond to these situations. Inspection and verification may be difficult when a host is unwilling,for valid reasons, to permit physical access to a site. We proposed a system of remote sensors which may be used to demonstrate compliance with Chemical Weapons Convention (CWC) challenge inspections even ff the inspector is physically excluded from a sensitive site. The system is based upon alternative-means-of-access provisions of the CWC. The Defense Nuclear Agency (DNA) funded design and construction of a system prototype, designated as MACS for Managed Access by Controlled Sensing. Features of the MACS design allow growth of the prototype into a versatile device for international monitoring of production facilities and other sites. MACS consists of instrumentation and communication equipment allowing site personnel to conduct a facility tour and perform acceptable measurements, while physically excluding the inspector from the facility. MACS consists of a base station used by the inspector, and a mobile unit used within the facility and manipulated by the facility staff. The base station and the mobile unit are at sign ed by a communication system, currently realized as a fiber optic cable. The mobile unit is equipped with television cameras and remote-reading distance-measuring equipment (DME) for use in verifying locations and dimensions. Global Positioning System receivers on the mobile unit provide both precise location and dead reckoning, suitable for tracking the mobile unit's position while within a building when satellite signals are not available

Automated ultrasonic inspection of nuclear plant components

International Nuclear Information System (INIS)

Baron, J.A.; Dolbey, M.P.

1982-01-01

For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods

Development of a piping thickness monitoring system using equipotential switching direct current potential drop method

International Nuclear Information System (INIS)

Kyung Ha, Ryu; Na Young, Lee; Il Soon, Hwang

2007-01-01

As nuclear power plants age, low alloy steel piping undergoes wall thickness reduction due to Flow Accelerated Corrosion (FAC). Persisting pipe rupture accidents prompted thinned pipe management programs. As a consequence extensive inspection activities are made based on the Ultrasonic Technique (UT). As the inspection points increase, time is needed to cover required inspection areas. In this paper, we present the Wide Range Monitoring (WiRM) concept with Equipotential Switching Direct Current Potential Drop (ES-DCPD) method by which FAC-active areas can be screened for detailed UT inspections. To apply ES-DCPD, we developed an electric resistance network model and electric field model based on Finite Element Analysis (FEA) to verify its feasibility. Experimentally we measured DCPD of the pipe elbow and confirmed the validity using UT inspections. For a more realistic validation test, we designed a high temperature flow test loop with environmental parameters turned for FAC simulation in the laboratory. Using electrochemical monitoring of water chemistry and local flow velocity prediction by computational fluid dynamic model, FAC rate is estimated. Based on the FAC prediction model and the simulation loop test, we plan to demonstrate the applicability of ES-DCPD in the PWR secondary environment. (authors)

14 CFR 145.223 - FAA inspections.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false FAA inspections. 145.223 Section 145.223... OTHER CERTIFICATED AGENCIES REPAIR STATIONS Operating Rules § 145.223 FAA inspections. (a) A certificated repair station must allow the FAA to inspect that repair station at any time to determine...

Generator acceptance test and inspection report

International Nuclear Information System (INIS)

Johns, B.R.

1997-01-01

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

Automated ultrasonic inspection using PULSDAT

International Nuclear Information System (INIS)

Naybour, P.J.

1992-01-01

PULSDAT (Portable Ultrasonic Data Acquisition Tool) is a system for recording the data from single probe automated ultrasonic inspections. It is one of a range of instruments and software developed by Nuclear Electric to carry out a wide variety of high quality ultrasonic inspections. These vary from simple semi-automated inspections through to multi-probe, highly automated ones. PULSDAT runs under the control of MIPS software, and collects data which is compatible with the GUIDE data display system. PULSDAT is therefore fully compatible with Nuclear Electric's multi-probe inspection systems and utilises all the reliability and quality assurance of the software. It is a rugged, portable system that can be used in areas of difficult access. The paper discusses the benefits of automated inspection and gives an outline of the main features of PULSDAT. Since April 1990 PULSDAT has been used in several applications within Nuclear Electric and this paper presents two examples: the first is a ferritic set-through nozzle and the second is an austenitic fillet weld. (Author)

In-service inspections of V-230 reactor

International Nuclear Information System (INIS)

Prepechal, J.

1984-01-01

It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

Intelligent Automated Nuclear Fuel Pellet Inspection System

International Nuclear Information System (INIS)

Keyvan, S.

1999-01-01

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

Current status of technology development on remote monitoring system

International Nuclear Information System (INIS)

Yoon, Wan Ki; Lee, Y. K.; Lee, Y. D.; Na, W. W.

1997-03-01

IAEA is planning to perform the remote monitoring system in nuclear facility in order to reinforce the economical and efficient inspection. National lab. in U.S. is developing the corresponding core technology and field trial will be done to test the remote monitoring system by considering the case that it replace the current safeguards system. U.S. setup the International Remote Monitoring Project to develop the technology. IAEA makes up remote monitoring team and setup the detail facility to apply remote monitoring system. Therefore, early participation in remote monitoring technology development will make contribution in international remote monitoring system and increase the transparency and confidence in domestic nuclear activities. (author). 12 refs., 20 figs

A review on transient monitoring systems

International Nuclear Information System (INIS)

Baylac, G.

1986-01-01

A good design must be followed by the continuous verification during service of design basis hypotheses. Transient monitoring techniques described hereafter were developed to fulfill this very logical requirement. They are shown to be useful to improve the reliability, operability, inspection and lifetime of components of the Reactor Coolant Pressure Boundary. 16 refs.

SICOM: On-site inspection systems

International Nuclear Information System (INIS)

Serna, J.J.; Quecedo, M.; Fernandez, J.R.

2002-01-01

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)

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.

Inspection of piping wall loss with flow accelerated corrosion accelerated simulation test

International Nuclear Information System (INIS)

Ryu, Kyung Ha; Kim, Ji Hak; Hwang, Il Soon; Lee, Na Young; Kim, Ji Hyun

2009-01-01

Flow Accelerated Corrosion (FAC) has become a hot issue for aging of passive components. Ultrasonic Technique (UT) has been adopted to inspect the secondary piping of Nuclear Power Plants (NPPs). UT, however, uses point detection method, which results in numerous detecting points and thus takes time. We developed an Equipotential Switching Direct Current Potential Drop (ES-DCPD) method to monitor the thickness of piping that covers wide range of piping at once time. Since the ES-DCPD method covers area, not a point, it needs less monitoring time. This can be a good approach to broad carbon steel piping system such as secondary piping of NPPs. In this paper, FAC accelerated simulation test results is described. We realized accelerated FAC phenomenon by 2 times test: 23.7% thinning in 216.7 hours and 51% thinning in 795 hours. These were monitored by ES-DCPD and traditional UT. Some parameters of water chemistry are monitored and controlled to accelerate FAC process. As sensitive factors on FAC, temperature and pH was changed during the test. The wall loss monitored results reflected these changes of water chemistry successfully. Developed electrodes are also applied to simulation loop to monitor water chemistry. (author)

Tritium release during inspection of reactor 'RA' at 'Vinca' institute

International Nuclear Information System (INIS)

Sipka, V.; Miljevic, N.; Grsic, Z.; Todorovic, D.; Radenkovic, M.

1997-01-01

Tritium content in daily precipitation, atmospheric water vapor inside of the reactor hall and around 'Vinca' Institute as well as in soil up to 800 m distance was monitoring during the regular inspection of the fuel channels. Tritium activity in the reactor hall air moisture was in the range from 0.022 to 6.7 MBq/m 3 . Tritium content in soil moisture between 12.7 and 530.9 Bq/l indicate a certain contamination due to tritium release in the environment, depending on the depth and distance from the place of release (author) [sr

Phased Array Ultrasonic Inspection of Titanium Forgings

International Nuclear Information System (INIS)

Howard, P.; Klaassen, R.; Kurkcu, N.; Barshinger, J.; Chalek, C.; Nieters, E.; Sun, Zongqi; Fromont, F. de

2007-01-01

Aerospace forging inspections typically use multiple, subsurface-focused sound beams in combination with digital C-scan image acquisition and display. Traditionally, forging inspections have been implemented using multiple single element, fixed focused transducers. Recent advances in phased array technology have made it possible to perform an equivalent inspection using a single phased array transducer. General Electric has developed a system to perform titanium forging inspection based on medical phased array technology and advanced image processing techniques. The components of that system and system performance for titanium inspection will be discussed

Boiler inspection manipulator for Torness Power Station

International Nuclear Information System (INIS)

Carrey, R.T.A.; Yule, I.Y.; Sibson, S.; Playle, M.J.

1996-01-01

The Advanced Gas-cooled Reactors at Torness and Heysham 2 are provided with dedicated access for remote inspection equipment. These in-service inspection (ISI) accesses comprise 12 penetrations above the core for inspection of the above core area and boilers, 12 below core penetrations for inspection of the lower boiler area and access through any of the 8 gas circulator penetrations for inspection of the sub-diagrid area. This paper describes a manipulator which will access the reactor from above the core via any of the 8 peripheral penetrations. (UK)

Rail inspection system based on iGPS

Science.gov (United States)

Fu, Xiaoyan; Wang, Mulan; Wen, Xiuping

2018-05-01

Track parameters include gauge, super elevation, cross level and so on, which could be calculated through the three-dimensional coordinates of the track. The rail inspection system based on iGPS (indoor/infrared GPS) was composed of base station, receiver, rail inspection frame, wireless communication unit, display and control unit and data processing unit. With the continuous movement of the inspection frame, the system could accurately inspect the coordinates of rail; realize the intelligent detection and precision measurement. According to principle of angle intersection measurement, the inspection model was structured, and detection process was given.

An intelligent fetal monitoring system

International Nuclear Information System (INIS)

Inaba, J.; Akatsuka, T.; Kubo, T.; Iwasaki, H.

1986-01-01

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

FRAMEWORK FOR STRUCTURAL ONLINE HEALTH MONITORING OF AGING AND DEGRADATION OF SECONDARY PIPING SYSTEMS DUE TO SOME ASPECTS OF EROSION

Energy Technology Data Exchange (ETDEWEB)

Gribok, Andrei V.; Agarwal, Vivek

2017-06-01

This paper describes the current state of research related to critical aspects of erosion and selected aspects of degradation of secondary components in nuclear power plants (NPPs). The paper also proposes a framework for online health monitoring of aging and degradation of secondary components. The framework consists of an integrated multi-sensor modality system, which can be used to monitor different piping configurations under different degradation conditions. The report analyses the currently known degradation mechanisms and available predictive models. Based on this analysis, the structural health monitoring framework is proposed. The Light Water Reactor Sustainability Program began to evaluate technologies that could be used to perform online monitoring of piping and other secondary system structural components in commercial NPPs. These online monitoring systems have the potential to identify when a more detailed inspection is needed using real time measurements, rather than at a pre-determined inspection interval. This transition to condition-based, risk-informed automated maintenance will contribute to a significant reduction of operations and maintenance costs that account for the majority of nuclear power generation costs. Furthermore, of the operations and maintenance costs in U.S. plants, approximately 80% are labor costs. To address the issue of rising operating costs and economic viability, in 2017, companies that operate the national nuclear energy fleet started the Delivering the Nuclear Promise Initiative, which is a 3 year program aimed at maintaining operational focus, increasing value, and improving efficiency. There is unanimous agreement between industry experts and academic researchers that identifying and prioritizing inspection locations in secondary piping systems (for example, in raw water piping or diesel piping) would eliminate many excessive in-service inspections. The proposed structural health monitoring framework takes aim at

Fuel assembly inspection device

International Nuclear Information System (INIS)

Yaginuma, Yoshitaka

1998-01-01

The present invention provides a device suitable to inspect appearance of fuel assemblies by photographing the appearance of fuel assemblies. Namely, the inspection device of the present invention measures bowing of fuel assembly or each of fuel rods or both of them based on the partially photographed images of fuel assembly. In this case, there is disposed a means which flashily projects images in the form of horizontal line from a direction intersecting obliquely relative to a horizontal cross section of the fuel assembly. A first image processing means separates the projected image pictures including projected images and calculates bowing. A second image processing means replaces the projected image pictures of the projected images based on projected images just before and after the photographing. Then, images for the measurement of bowing and images for inspection can be obtained simultaneously. As a result, the time required for the photographing can be shortened, the time for inspection can be shortened and an effect of preventing deterioration of photographing means by radiation rays can be provided. (I.S.)

Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

OpenAIRE

2010-01-01

In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the technical conditions of cars at inspection as well as that of cars involved in crashes were studied. Tyre pressure will also be discussed in this fact sheet.

Plant inspection and maintenance technology

International Nuclear Information System (INIS)

Miyahara, Masatoshi; Kanazawa, Masafumi

1995-01-01

The article reports on information systems and related tools that support routine inspection and preventive maintenance activities, which contribute to safer plant operation and increase plant operating duty. Tools include the Mitsubishi Electric Reliability and Availability Upgrade Program-Nuclear (MELRAP-N), which supports the general evolution of industry operating experiences, periodic component replacement management, management of discontinued and modified components, periodic inspection item management, and periodic inspection workplace management. The article also introduces a comprehensive preventive maintenance management system currently under development. (author)

Turning inspection regulations into training tools

International Nuclear Information System (INIS)

Finley, D.; Wheatcraft, D.

1996-01-01

In response to suggestions from internal and State of California auditors, the Hazardous Waste Management Division (HWM) at Lawrence Livermore National Laboratory prepared an Inspection Schedule and Guidance Document that summarizes the Laboratory's inspection schedule and procedures for waste treatment, storage, and disposal facilities (TSDFs). Because it explains and comments in detail on the inspection schedule, forms, and procedures, this document is a centralized reference for HWM managers and personnel performing TSDF inspections at the Laboratory. It is also a training tool for experienced and new inspectors, standardizing the inspections of personnel with experience and explaining to novices what to look for and why. This poster presentation traces the team effort that created this document and provides specific examples of how the document was developed and how it is used

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

International Nuclear Information System (INIS)

2015-01-01

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.

Licensee Contractor and vendor inspection status report

International Nuclear Information System (INIS)

1992-01-01

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

Licensee contractor and vendor inspection status report

International Nuclear Information System (INIS)

1993-08-01

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

Licensee contractor and Vendor Inspection status report