WorldWideScience

Sample records for internal inspection systems

  1. Internal testing of pipe systems with IRIS inspection system

    International Nuclear Information System (INIS)

    1986-01-01

    The internal piping inspection system IRIS allows inside testing of pipes with an internal diameter of NW 70 as a minimum, and of any horizontal or vertical layout of the piping system. Visual testing is done by means of an integrated CCD video system with high resolution power. Technical data are given and examples of applications, in the German and English language. (DG) [de

  2. Optimizing the design of international safeguards inspection systems

    International Nuclear Information System (INIS)

    Markin, J.T.; Coulter, C.A.; Gutmacher, R.G.; Whitty, W.J.

    1983-01-01

    Efficient implementation of international inspections for verifying the operation of a nuclear facility requires that available resources be allocated among inspection activities to maximize detection of misoperation. This report describes a design and evaluation method for selecting an inspection system that is optimal for accomplishing inspection objectives. The discussion includes methods for identifying system objectives, defining performance measures, and choosing between candidate systems. Optimization theory is applied in selecting the most preferred inspection design for a single nuclear facility, and an extension to optimal allocation of inspection resources among States containing multiple facilities is outlined. 3 figures, 5 tables

  3. Wheel inspection system environment.

    Science.gov (United States)

    2008-11-18

    International Electronic Machines Corporation (IEM) has developed and is now marketing a state-of-the-art Wheel Inspection System Environment (WISE). WISE provides wheel profile and dimensional measurements, i.e. rim thickness, flange height, flange ...

  4. Wall thickness measurements of tubes by Internal Rotary Inspection System (IRIS)- a comparative study with metallography

    International Nuclear Information System (INIS)

    Subramanian, C.V.; Joseph, A.; Ramesh, A.S.; Jayakumar, T.; Kalyanasundaram, P.; Baldev Raj

    1996-01-01

    Internal Rotary Inspection System (IRIS) is a relatively new ultrasonic system of heat exchanger/ steam condenser tubes and pipelines for measurement of wall thinning and pitting due to corrosion. The wall thickness measurements made during a scan around the circumference of the tube are displayed as a stationary rectilinear display of circumferential cross section (Bscan) of the tube. The paper describes the results obtained on tubes of various materials used in process industries having corrosion on inner and outer surfaces of the tube. (author)

  5. 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)

  6. MACS as a tool for international inspections

    International Nuclear Information System (INIS)

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

    1995-01-01

    The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites

  7. MACS as a tool for international inspections

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-08-01

    The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites.

  8. 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.

  9. 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.

  10. 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

  11. 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)

  12. 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

  13. 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

  14. 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

  15. Inspection and repair of reactor pressure vessel (RPV) internals

    International Nuclear Information System (INIS)

    Bohmann, W.; Poetz, F.; Nicolai, M.

    1996-01-01

    The past 10 years of operation of light water reactors were characterized by intensive inspection- and repair work on vital components. For boiling water reactors (BWR) it was typical to totally replace the piping system and for pressurized water reactors (PWR) it was the step to complete steam generator (SG) replacement - besides the development of increasingly diligent inspection and repair methods for SG tubes. It can be expected that in the 10 years to come the development of inspection- and repair methods will be aimed mainly at the core internals of BWR's as well as PWR's. Our prediction is that before the end of this decade a first complete replacement of these components will be performed. Already to date a broad range of techniques are available which enable the utilities to carry out inspections and repair of components of core internals in a relatively short time and acceptable expenses. Using examples such as Fuel Alignment Pin Inspection and Replacement, Baffle Former Bolt Inspection and Replacement, Core Barrel Former Bolt Inspection which are typical for PWR's we will in the following describe the existing methods, their development and - last but not least - their successful utilization. What is going to happen in the future? Ageing of the operating plants will continue, thus requesting the plant operators as well as the service companies to work on advanced technologies to fulfill the needs of the industry. (author)

  16. Internal ultrasonic inspection of flexible pipe

    Energy Technology Data Exchange (ETDEWEB)

    Baltzersen, O. (IKU Petroleumsforskning A/S, Trondheim (Norway) Norwegian Inst. of Tech., Trondheim (Norway). Div. of Petroleum Engineering and Applied Geophysics); Waag, T.I. (IKU Petroleumsforskning A/S, Trondheim (Norway))

    1993-10-01

    Methods for internal ultrasonic inspection of flexible pipe have been investigated through experiments with a short sample of Coflexip pipe. Ultrasonic backscatter methods using normal and non-normal incidence have been used for qualitative high contrast ultrasonic imaging of the inner surface of the pipe. Analysis of the internal cross-section has been performed based on the use of a non-contact ultrasonic caliper, and processing procedures which enable calculation of, and compensation for, eccentricity of the tool in the pipe. The methods developed can be used to quantitatively estimate the thickness of the internal carcass, and perform high resolution topographic mapping of the inner surface. (Author)

  17. Guided acoustic wave inspection system

    Science.gov (United States)

    Chinn, Diane J.

    2004-10-05

    A system for inspecting a conduit for undesirable characteristics. A transducer system induces guided acoustic waves onto said conduit. The transducer system detects the undesirable characteristics of the conduit by receiving guided acoustic waves that contain information about the undesirable characteristics. The conduit has at least two sides and the transducer system utilizes flexural modes of propagation to provide inspection using access from only the one side of the conduit. Cracking is detected with pulse-echo testing using one transducer to both send and receive the guided acoustic waves. Thinning is detected in through-transmission testing where one transducer sends and another transducer receives the guided acoustic waves.

  18. Complex licences: a decade of experience with internal inspections

    International Nuclear Information System (INIS)

    Boersma, Hielke Freerk; Bunskoeke, Erik J.

    2008-01-01

    Full text: In 2008 the University of Groningen has ten years of experience with the system of complex broad licences. This system was introduced on a larger scale in the Netherlands in the last decade of the twentieth century. Its main characteristics are an internal radiation protection organization and a system of internal permits or licences for all applications of ionizing radiation along with periodical inspections. Since 1998/9 we yearly conduct inspections of all users of ionizing radiation within the University of Groningen. In our presentation we will discuss the general scheme for these inspections as well as the development of its results over the past decade. Following a period of habituation the last few years show a adequate and continuous level of radiation protection. It is also concluded that continuation of the inspection projects is a prerequisite to preserve this situation. Combined with the inspection project of 2007 an informal study of the 'customer'-satisfaction with respect to various aspects of the radiation protection organization was performed. Our data were collected using a questionnaire filled out by local radiation safety officers. In this contribution detailed results of this investigation will be presented. Preliminary results show that the overall appreciation of the radiation protection organization is qualified as 'good'. (author)

  19. Visual inspection of vessel internals; Visuelle Inspektion von Kerneinbauten

    Energy Technology Data Exchange (ETDEWEB)

    Rabe, G. [Siemens AG KWU, Erlangen (Germany)

    1999-08-01

    Visual inspection has matured to a qualified testing method and has become a standard method for inspection of reactor pressure vessels. Until today, all known defects in RPV internals have been detected by visual inspection. The codes KTA 3204 and DIN 25435-4 describe the framework conditions and requirements for visual inspections, which should be adhered to to the most possible extent. Visual inspections are carried by now at all RPV internals, also at those where access is difficult and limited. The inspection robot SUSI is applied in most cases. The camera and manipulator technology meanwhile has been upgraded to a standard performance quality allowing reliable, fast and easy visual inspection. The personnel is trained accordingly, so as to keep abreast with enhancements. Qualification of the inspection system has been simplified and standardised to a large extent. (orig/CB) [Deutsch] Die Sichtpruefung ist zu einem qualifizierten Pruefverfahren gereift und hat bei der Inspektion der RDB-Einbauten einen festen Platz eingenommen. Bisher wurden alle bekannten Schaeden an den RDB-Einbauten bei der Sichtpruefung festgestellt. In der KTA 3204 und der DIN 25435-4 sind die Rahmenbedingungen und Anforderungen an die Sichtpruefung beschrieben, die es gilt, weitestgehend einzuhalten. Mittlerweile werden an allen RDB-Einbauten, auch an den nur bedingt zugaenglichen, Sichtpruefungen vorgenommen. Dabei hat das Inspektionsfahrzeug SUSI inzwischen den breitesten Raum eingenommen. Die Entwicklung der Kamera- und Manipulatortechnik hat inzwischen einen Stand erreicht, der eine sichere, schnelle und einfache Sichtpruefung zulaesst. Das Pruefpersonal wird laufend fuer die Sichtpruefung geschult und qualifiziert. Die Qualifizierung des Inspektionssystems wurde weitestgehend vereinfacht und standardisiert. (orig.)

  20. 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)

  1. 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)

  2. Remote inspection system for nuclear power plants

    International Nuclear Information System (INIS)

    Inagaki, K.; Fujii, M.; Doi, A.; Harima, T.

    1977-01-01

    A remote inspection system for nuclear power plants was constructed based on an analysis of inspections performed by an operator on patrol. This system consists of an operator's console and a remote station. The remote station, equipped with five kinds of sensors, is steered along the inspection route by a photoelectric guiding system or may be manually controlled from an operator's console in a main control room. Signals for control and inspection data are multiplexed and transmitted through a coaxial cable

  3. Development of an optical inspection bench for the inspection of internal surfaces of 650 MHz SCRF cavities

    International Nuclear Information System (INIS)

    Kokil, S.V.; Kane, G.V.; Raghavendra, S.; Chauhan, S.K.; Rajpoot, D.S.; Oraon, B.; Om Prakash; Joshi, S.C.

    2015-01-01

    An optical inspection system has been developed for inspection of internal surfaces of 650 MHz superconducting RF cavities. The cavity parts are welded either using Electron Beam or Laser Beam Welding for making a good quality of weld joints. Surface defects like pits, scratches, welding spatters etc. on the internal surface of the cavity deteriorates cavity performance. Surface quality of the cavity equator joint plays an important role in the cavity performance. To study the quality of equator surface, the inspection bench offers high resolution images with a linear resolution of 45 m/pixel at a distance of ∼200 mm. The bench comprises of two major sub-systems, optical imaging system and cavity positioning system. A digital camera and multi coloured illumination system is used to obtain high resolution images. The camera is mounted inside a long cylindrical tube. The cylindrical tube can be inserted into a SCRF cavity. The length of the cylinder is long enough to inspect five-cell 650 MHz SCRF cavity. The cavity is placed on a set of PTFE rollers, which are mounted on a trolley. The cavity can be moved linearly with the help of ball screw-servomotor mechanism. The camera along with cylindrical tube can be rotated around its axis with a stepper motor to scan the cavity's internal surface. The paper presents the details about the optical inspection bench and optical inspection results. (author)

  4. 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

  5. Mechanized ultrasonic inspection of austenitic pipe systems

    International Nuclear Information System (INIS)

    Dressler, K.; Luecking, J.; Medenbach, S.

    1999-01-01

    The contribution explains the system of standard testing methods elaborated by ABB ZAQ GmbH for inspection of austenitic plant components. The inspection tasks explained in greater detail are basic materials testing (straight pipes, bends, and pipe specials), and inspection of welds and dissimilar welds. The techniques discussed in detail are those for detection and sizing of defects. (orig./CB) [de

  6. Optimal allocation of international atomic energy agency inspection resources

    International Nuclear Information System (INIS)

    Markin, J.T.

    1987-01-01

    Each year the Department of Safeguards of the International Atomic Energy Agency (IAEA) conducts inspections to confirm that nuclear materials and facilities are employed for peaceful purposes. Because of limited inspection resources, however, the IAEA cannot fully attain its safeguards goals either quantitatively as measured by the inspection effort negotiated in the facility attachments or qualitatively as measured by the IAEA criteria for evaluating attainment of safeguards goals. Under current IAEA procedures the allocation of inspection resources assigns essentially equal inspection effort to facilities of the same type. An alternative approach would incorporate consideration of all material categories and facilities to be assigned inspection resources when allocating effort to a particular facility. One such method for allocating inspection resources is based on the IAEA criteria. The criteria provide a framework for allocating inspection effort that includes a ranking of material types according to their safeguards importance, an implicit definition of inspection activities for each material and facility type, and criteria for judging the attainment of safeguards goals in terms of the quality and frequency of these inspection activities. This framework is applicable to resource allocation for an arbitrary group of facilities such as a state's fuel cycle, the facilities inspected by an operations division, or all of the facilities inspected by the IAEA

  7. Project in fiscal 2000 of developing international standards for supporting new industries. Standardization of evaluation method for gene inspection system; 2000 nendo shinki sangyo shiengata kokusai hyojunka kaihatsu jigyo seika hokokusho. Idenshi kensa system no hyoka hoho no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Discussions and deliberations were given by the comprehensive survey committee on standardization of a total gene inspection system from specimen adjustment necessary for the gene inspection system to data processing. This paper summarizes the achievements in fiscal 2000. In standardization related to the specimen procedure and the inspection technique, the specimen storing method and the report statement contents were established. In addition, verification was made on the heat-resistant enzyme reagent and such measuring devices as the electric migration device and the photographing device. Discussions were given on standard substances used in the gene inspection. Regarding the K562 cell strain, cross-checking was performed in three institutions, wherein discussions were given on interchangeability of the inspection results, and the usefulness of the K562 cell as a standard substance. As a result, all the three institutions have come to an agreement on the Southern method, the FISH method and the RT-PCR method, but not on the real-time PT-PCR method, leaving the subject as the future assignment. In the survey for Europe and America, visits were made to AFNOR, CEN, DIN, FDA and CAP for the attempt of collecting information and establishing international exchange. (NEDO)

  8. Optimal allocation of International Atomic Energy Agency inspection resources

    International Nuclear Information System (INIS)

    Markin, J.T.

    1987-12-01

    The Safeguards Department of the International Atomic Energy Agency (IAEA) conducts inspections to assure the peaceful use of a state's nuclear materials and facilities. Because of limited resources for conducting inspections, the careful disposition of inspection effort among these facilities is essential if the IAEA is to attain its safeguards goals. This report describes an optimization procedure for assigning an inspection effort to maximize attainment of IAEA goals. The procedure does not require quantitative estimates of safeguards effectiveness, material value, or facility importance. Instead, the optimization is based on qualitative, relative prioritizations of inspection activities and materials to be safeguarded. This allocation framework is applicable to an arbitrary group of facilities such as a state's fuel cycle, the facilities inspected by an operations division, or all of the facilities inspected by the IAEA

  9. 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

  10. 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

  11. A novel visual pipework inspection system

    Science.gov (United States)

    Summan, Rahul; Jackson, William; Dobie, Gordon; MacLeod, Charles; Mineo, Carmelo; West, Graeme; Offin, Douglas; Bolton, Gary; Marshall, Stephen; Lille, Alexandre

    2018-04-01

    The interior visual inspection of pipelines in the nuclear industry is a safety critical activity conducted during outages to ensure the continued safe and reliable operation of plant. Typically, the video output by a manually deployed probe is viewed by an operator looking to identify and localize surface defects such as corrosion, erosion and pitting. However, it is very challenging to estimate the nature and extent of defects by viewing a large structure through a relatively small field of view. This work describes a new visual inspection system employing photogrammetry using a fisheye camera and a structured light system to map the internal geometry of pipelines by generating a photorealistic, geometrically accurate surface model. The error of the system output was evaluated through comparison to a ground truth laser scan (ATOS GOM Triple Scan) of a nuclear grade split pipe sample (stainless steel 304L, 80mm internal diameter) containing defects representative of the application - the error was found to be submillimeter across the sample.

  12. 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.

  13. Development of an automatic reactor inspection system

    International Nuclear Information System (INIS)

    Kim, Jae Hee; Eom, Heung Seop; Lee, Jae Cheol; Choi, Yoo Raek; Moon, Soon Seung

    2002-02-01

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

  14. System for inspection of stacked cargo containers

    Science.gov (United States)

    Derenzo, Stephen [Pinole, CA

    2011-08-16

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

  15. Periodic inspections of the primary system

    International Nuclear Information System (INIS)

    Dufour, L.B.

    1978-01-01

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

  16. 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

  17. 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.

  18. Innovative inspection system for reactor pressure vessels

    International Nuclear Information System (INIS)

    Mertens, K.; Trautmann, H.

    1999-01-01

    The versatile, compact and modern underwater systems described, the DELPHIN manipulators and MIDAS submarines, are innovative systems enabling RPV inspections at considerably reduced efforts and time, thus reducing the total time required for ISI of reactors. (orig./CB) [de

  19. The IAEA Inspections: Creating a Collective Security System

    International Nuclear Information System (INIS)

    Le Guelte, Georges

    2003-01-01

    Through their successes, their achievements and the hopes they raised of a world where the law would replace the arbitrary, but also through the failures imputed to them and the fragility of their action, the inspections of the International Atomic Energy Agency (IAEA) have become a symbol of the capacities, the limits, and the weaknesses of the international system founded in 1945 by the UN Charter. Originally, their objective was much more limited. Historical developments - the Cold War, in particular - have turned the inspections into the major instrument of a unique mechanism of collective security, that is recovering its full significance in the current international context

  20. Noncontacting Optical Measurement And Inspection Systems

    Science.gov (United States)

    Asher, Jeffrey A.; Jackson, Robert L.

    1986-10-01

    Product inspection continues to play a growing role in the improvement of quality and reduction of scrap. Recent emphasis on precision measurements and in-process inspection have been a driving force for the development of noncontacting sensors. Noncontacting sensors can provide long term, unattended use due to the lack of sensor wear. Further, in applications where, sensor contact can damage or geometrically change the part to be measured or inspected, noncontacting sensors are the only technical approach available. MTI is involved in the development and sale of noncontacting sensors and custom inspection systems. This paper will review the recent advances in noncontacting sensor development. Machine vision and fiber optics sensor systems are finding a wide variety of industrial inspection applications. This paper will provide detailed examples of several state-of-the-art applications for these noncontacting sensors.

  1. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-01

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

  3. Study of a risk-based piping inspection guideline system.

    Science.gov (United States)

    Tien, Shiaw-Wen; Hwang, Wen-Tsung; Tsai, Chih-Hung

    2007-02-01

    A risk-based inspection system and a piping inspection guideline model were developed in this study. The research procedure consists of two parts--the building of a risk-based inspection model for piping and the construction of a risk-based piping inspection guideline model. Field visits at the plant were conducted to develop the risk-based inspection and strategic analysis system. A knowledge-based model had been built in accordance with international standards and local government regulations, and the rational unified process was applied for reducing the discrepancy in the development of the models. The models had been designed to analyze damage factors, damage models, and potential damage positions of piping in the petrochemical plants. The purpose of this study was to provide inspection-related personnel with the optimal planning tools for piping inspections, hence, to enable effective predictions of potential piping risks and to enhance the better degree of safety in plant operations that the petrochemical industries can be expected to achieve. A risk analysis was conducted on the piping system of a petrochemical plant. The outcome indicated that most of the risks resulted from a small number of pipelines.

  4. International inspection activity impacts upon DOE safeguards requirements

    International Nuclear Information System (INIS)

    Zack, N.R.

    1995-01-01

    The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies

  5. Nuclear fuel pellet inspection system

    International Nuclear Information System (INIS)

    Ahmed, H.J.; Beatty, J.M.; Kugler, R.W.

    1992-01-01

    At least one axially extending linear portion of the peripheral surface of the pellet is optically sensed, a set of digital values representative of the pellet surface is generated, and the set is compared to a predetermined standard. Groups of adjacent locations on the surface of the pellet having values greater or less than the predetermined standard are identified, and the pellet is rejected, when a flawed area exceeds a predetermined size. During inspection, the pellet is moved axially through an inspection station by parallel support rolls, spaced by a distance less than the pellet diameter. The rolls are rotated upward and outward from each other, rotating the pellet, and chain dogs are positioned between the spaced rolls for engaging a pellet and moving it along the rolls. The pellet is rejected if its peripheral surface area is too great, and a reference pellet may be used. (author)

  6. 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

  7. 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.

  8. Remote inspection system for hazardous sites

    International Nuclear Information System (INIS)

    Redd, J.; Borst, C.; Volz, R.A.; Everett, L.J.

    1999-04-01

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

  9. Steam Generator Inspection Planning Expert System

    International Nuclear Information System (INIS)

    Rzasa, P.

    1987-01-01

    Applying Artificial Intelligence technology to steam generator non-destructive examination (NDE) can help identify high risk locations in steam generators and can aid in preparing technical specification compliant eddy current test (ECT) programs. A steam Generator Inspection Planning Expert System has been developed which can assist NDE or utility personnel in planning ECT programs. This system represents and processes its information using an object oriented declarative knowledge base, heuristic rules, and symbolic information processing, three artificial intelligence based techniques incorporated in the design. The output of the system is an automated generation of ECT programs. Used in an outage inspection, this system significantly reduced planning time

  10. 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)

  11. Review of inspection of Torness reactor internals using remote techniques

    International Nuclear Information System (INIS)

    Dynan, J.

    1993-01-01

    Inspection of reactor internals is increasingly being achieved by deployment of cameras into areas of sometimes high radiation fields using manipulators. The manipulators have been developed over a number of years and from a variety of sources and those provided at Torness can maybe be seen to be the state of the art development of such machines for AGRS. Torness and Heysham 2 reactors were specifically designed for inspection using remote techniques and special facilities have been provided for this purpose. This paper is written by an operator and not a manipulator specialist and is intended to show what the operator needs versus what the designer gave him. (author)

  12. Handling system for nuclear fuel pellet inspection

    International Nuclear Information System (INIS)

    Nyman, D.H.; McLemore, D.R.; Sturges, R.H.

    1978-11-01

    HEDL is developing automated fabrication equipment for fast reactor fuel. A major inspection operation in the process is the gaging of fuel pellets. A key element in the system has been the development of a handling system that reliably moves pellets at the rate of three per second without product damage or excessive equipment wear

  13. Mobile waste inspection real time radiography system

    International Nuclear Information System (INIS)

    Vigil, J.; Taggart, D.; Betts, S.; Rael, C.; Martinez, F.; Mendez, J.

    1995-01-01

    The 450-KeV Mobile Real Time Radiography System was designed and purchased to inspect containers of radioactive waste produced at Los Alamos National Laboratory (LANL). The Mobile Real Time Radiography System has the capability of inspecting waste containers of various sizes from 5-gal. buckets to standard waste boxes (SWB, dimensions 54.5 in. x 71 in. x 37 in.). The fact that this unit is mobile makes it an attractive alternative to the costly road closures associated with moving waste from the waste generator to storage or disposal facilities

  14. Status on system inspection and preventive maintenance of HANARO

    International Nuclear Information System (INIS)

    Kim, Young-Ki; Cho, Yeong-Garp; Kwag, Byung-Ho

    1999-01-01

    The HANARO is a 30 MW open pool type multi-purpose research reactor with forced light water coolant/moderator flows and heavy water annular reflector. The relatively small reactor core uses a low enriched fuel and is designed to maximize the power density, thus providing the required neutron flux for various research activities. It is mainly used for radioisotope production, nuclear material testing and neutron physics experiments. The initial criticality was achieved February 1995. Considering the importance of their functionality from the safety point of view, some components and equipment are categorized into a nuclear safety grade. There are three different inspection activities for the various reactor systems and components - a Surveillance Inspection(SI) for the safety grades and a Periodic Inspection (PI) for the non-safety grades and In-Service Inspection (ISI) for the ASME Sec.III components. All of the SIs are specified and required by the safety analysis report. The SI also differs from the PI in such a point that all kinds of activities for the SIs should be accompanied by an appropriate quality assurance, while for the PIs it is not necessarily mandatory. In addition, the inspection results for the SIs should go through an examination from regulatory body every two years and specific functions of the critical components or systems are demonstrated under the witness by the governmental inspector. The ISI is required and carried out as per international codes and standards as well as Korean atomic energy regulations. There are 54 SIs, 25 PIs and 4 ISIs for the HANARO. This paper concentrates on the managing strategy and its practices for the SIs and ISIs of the safety-related components, currently being done at HANARO. Most parts of the inspections fall into a group for the periodic performance testing and/or equipment calibration. Some mechanical inspections like a torque measurement are grouped into a preventive maintenance. Lastly the ASME Sec

  15. Machine vision systems using machine learning for industrial product inspection

    Science.gov (United States)

    Lu, Yi; Chen, Tie Q.; Chen, Jie; Zhang, Jian; Tisler, Anthony

    2002-02-01

    Machine vision inspection requires efficient processing time and accurate results. In this paper, we present a machine vision inspection architecture, SMV (Smart Machine Vision). SMV decomposes a machine vision inspection problem into two stages, Learning Inspection Features (LIF), and On-Line Inspection (OLI). The LIF is designed to learn visual inspection features from design data and/or from inspection products. During the OLI stage, the inspection system uses the knowledge learnt by the LIF component to inspect the visual features of products. In this paper we will present two machine vision inspection systems developed under the SMV architecture for two different types of products, Printed Circuit Board (PCB) and Vacuum Florescent Displaying (VFD) boards. In the VFD board inspection system, the LIF component learns inspection features from a VFD board and its displaying patterns. In the PCB board inspection system, the LIF learns the inspection features from the CAD file of a PCB board. In both systems, the LIF component also incorporates interactive learning to make the inspection system more powerful and efficient. The VFD system has been deployed successfully in three different manufacturing companies and the PCB inspection system is the process of being deployed in a manufacturing plant.

  16. Algorithm design of liquid lens inspection system

    Science.gov (United States)

    Hsieh, Lu-Lin; Wang, Chun-Chieh

    2008-08-01

    In mobile lens domain, the glass lens is often to be applied in high-resolution requirement situation; but the glass zoom lens needs to be collocated with movable machinery and voice-coil motor, which usually arises some space limits in minimum design. In high level molding component technology development, the appearance of liquid lens has become the focus of mobile phone and digital camera companies. The liquid lens sets with solid optical lens and driving circuit has replaced the original components. As a result, the volume requirement is decreased to merely 50% of the original design. Besides, with the high focus adjusting speed, low energy requirement, high durability, and low-cost manufacturing process, the liquid lens shows advantages in the competitive market. In the past, authors only need to inspect the scrape defect made by external force for the glass lens. As to the liquid lens, authors need to inspect the state of four different structural layers due to the different design and structure. In this paper, authors apply machine vision and digital image processing technology to administer inspections in the particular layer according to the needs of users. According to our experiment results, the algorithm proposed can automatically delete non-focus background, extract the region of interest, find out and analyze the defects efficiently in the particular layer. In the future, authors will combine the algorithm of the system with automatic-focus technology to implement the inside inspection based on the product inspective demands.

  17. A stereoscopic television system for reactor inspection

    International Nuclear Information System (INIS)

    Friend, D.B.; Jones, A.

    1980-03-01

    A stereoscopic television system suitable for reactor inspection has been developed. Right and left eye views, obtained from two conventional black and white cameras, are displayed by the anaglyph technique and observers wear appropriately coloured viewing spectacles. All camera functions, such as zoom, focus and toe-in are remotely controlled. A laboratory experiment is described which demonstrates the increase in spatial awareness afforded by the use of stereo television and illustrates its potential in the supervision of remote handling tasks. Typical depth resolutions of 3mm at 1m and 10mm at 2m have been achieved with the reactor instrument. Trials undertaken during routine inspection at Oldbury Power Station in June 1978 are described. They demonstrate that stereoscopic television can indeed improve the convenience of remote handling and that the added display realism is beneficial in visual inspection. (author)

  18. Optimal inspection strategies for offshore structural systems

    DEFF Research Database (Denmark)

    Faber, M. H.; Sorensen, J. D.; Kroon, I. B.

    1992-01-01

    a mathematical framework for the estimation of the failure and repair costs a.ssociated with systems failure. Further a strategy for selecting the components to inspect based on decision tree analysis is suggested. Methods and analysis schemes are illustrated by a simple example....

  19. Fuel visual inspection system of the RTMIII

    International Nuclear Information System (INIS)

    Delfin L, A.; Castaneda J, G.; Mazon R, R.; Aguilar H, F.

    2007-01-01

    The International Atomic Energy Agency (IAEA) through the RLA/04/18 project, Management of Irradiated Fuel in Research Reactors, it recommended among other that the participant countries (Brazil, Argentina, Chile, Peru and Mexico), develop tools to assure the integrity of the nuclear fuels used in the research reactors. The TRIGA Mark lll reactor (RTMIII) of the ININ, designed and built a system of visual inspection, that it uses a high radiation camera and image digitalisation. The project considers safety conditions of the personnel that carried out the activities of visual inspection, for that which the tool dives in the pool of the RTMIII, being held by an end in the superior part of the aluminium liner of the Reactor like it is shown in the plane No. 1. The primordial unit of the system is the visual equipment that corresponds to a camera of the Hydro-Technologie (HYTEC) VSLT 410N mark, designed to work in atmospheres under the water and/or in places of high risk. The camera has an unit of motorized orientation of stainless steel that can be rotated unboundedly in both senses, with variable speed by means of a control lever from the control unit. Together to this orientation unit is found the camera head, the one which is contained in an unit of motorized inclination of stainless steel that can be rotated azimuthally up to 370 degrees in both senses. The operation conditions of the camera are the following ones, temperature: 0 to 50 C, dose speed: ≤ 50 rad/h, operation depth: ≤ 30 mts, humidity (control unit): ≤ 80%. From the control unit it is derived an external device plug-n-play TV-Usb Aver Media marks whose function is to decode the video signal sent by the control unit and to transmit it to the computer where the image is captured in picture or video that is analyzed later on with any software ad hoc, that in our case we use the Quantikov Image Analyzer program for Windows 98 of the Dr. Lucio C. M. Pinto from Brazil who participates in the RLA/04

  20. System of leak inspection of irradiated fuel

    International Nuclear Information System (INIS)

    Delfin L, A.; Castaneda J, G.; Mazon R, R.; Aguilar H, F.

    2007-01-01

    The International Atomic Energy Agency (IAEA) through the project RLA/04/18 Irradiated Fuel Management in Research reactors, recommended among other that the participant countries (Brazil, Argentina, Chile, Peru and Mexico), develop the sipping tool to generate registrations of the state that keep the irradiated fuels in the facilities of each country. The TRIGA Mark lll Reactor (RTMIII) Department, generated a project that it is based on the dimensions of the used fuel by the RTMIII, for design and to build an inspection system of irradiated fuel well known as SIPPING. This technique, provides a high grade of accuracy in the detection of gassy fission products or liquids that escape from the enveloping of fuels that have flaws or flights. The operation process of the SIPPING is carried out generating the migration of fission products through the creation of a pressure differential gas or vacuum to identify fuel assemblies failed by means of the detection of the xenon and/or krypton presence. The SIPPING system, is a device in revolver form with 4 tangential nozzles, which will discharge the fluid between the external surface of the enveloping of the fuel and the interior surface of the encircling one; the device was designed with independent pieces, with threaded joining and with stamps to impede flights of the fluid toward the exterior of the system. The System homogenizes and it distributes the fluid pressure so that the 4 nozzles work to equality of conditions, for what the device was designed in 3 pieces, an internal that is denominated revolver, one external that calls cover, and a joining called mamelon that will unite with the main encircling of the system. The detection of fission products in failed fuels, its require that inside the encircling one where the irradiated fuel element is introduced, be generated a pressure differential of gas or vacuum, and that it allows the samples extraction of water. For what generated a top for the encircling with the

  1. Sensor system for web inspection

    Science.gov (United States)

    Sleefe, Gerard E.; Rudnick, Thomas J.; Novak, James L.

    2002-01-01

    A system for electrically measuring variations over a flexible web has a capacitive sensor including spaced electrically conductive, transmit and receive electrodes mounted on a flexible substrate. The sensor is held against a flexible web with sufficient force to deflect the path of the web, which moves relative to the sensor.

  2. 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

  3. An automated miniature robotic vehicle inspection system

    Energy Technology Data Exchange (ETDEWEB)

    Dobie, Gordon; Summan, Rahul; MacLeod, Charles; Pierce, Gareth; Galbraith, Walter [Centre for Ultrasonic Engineering, University of Strathclyde, 204 George Street, Glasgow, G1 1XW (United Kingdom)

    2014-02-18

    A novel, autonomous reconfigurable robotic inspection system for quantitative NDE mapping is presented. The system consists of a fleet of wireless (802.11g) miniature robotic vehicles, each approximately 175 × 125 × 85 mm with magnetic wheels that enable them to inspect industrial structures such as storage tanks, chimneys and large diameter pipe work. The robots carry one of a number of payloads including a two channel MFL sensor, a 5 MHz dry coupled UT thickness wheel probe and a machine vision camera that images the surface. The system creates an NDE map of the structure overlaying results onto a 3D model in real time. The authors provide an overview of the robot design, data fusion algorithms (positioning and NDE) and visualization software.

  4. An automated miniature robotic vehicle inspection system

    International Nuclear Information System (INIS)

    Dobie, Gordon; Summan, Rahul; MacLeod, Charles; Pierce, Gareth; Galbraith, Walter

    2014-01-01

    A novel, autonomous reconfigurable robotic inspection system for quantitative NDE mapping is presented. The system consists of a fleet of wireless (802.11g) miniature robotic vehicles, each approximately 175 × 125 × 85 mm with magnetic wheels that enable them to inspect industrial structures such as storage tanks, chimneys and large diameter pipe work. The robots carry one of a number of payloads including a two channel MFL sensor, a 5 MHz dry coupled UT thickness wheel probe and a machine vision camera that images the surface. The system creates an NDE map of the structure overlaying results onto a 3D model in real time. The authors provide an overview of the robot design, data fusion algorithms (positioning and NDE) and visualization software

  5. Detector correction in large container inspection systems

    CERN Document Server

    Kang Ke Jun; Chen Zhi Qiang

    2002-01-01

    In large container inspection systems, the image is constructed by parallel scanning with a one-dimensional detector array with a linac used as the X-ray source. The linear nonuniformity and nonlinearity of multiple detectors and the nonuniform intensity distribution of the X-ray sector beam result in horizontal striations in the scan image. This greatly impairs the image quality, so the image needs to be corrected. The correction parameters are determined experimentally by scaling the detector responses at multiple points with logarithm interpolation of the results. The horizontal striations are eliminated by modifying the original image data with the correction parameters. This method has proven to be effective and applicable in large container inspection systems

  6. PIPEBOT: a mobile system for duct inspection

    Energy Technology Data Exchange (ETDEWEB)

    Estrada, Emanuel; Goncalves, Eder Mateus; Botelho, Silvia; Oliveira, Vinicius; Souto Junior, Humberto; Almeida, Renan de; Mello Junior, Claudio; Santos, Thiago [Universidade Federal do Rio Grande (FURG), RS (Brazil); Gulles, Roger [Universidade Tecnologica Federal do Parana (UTFPR), Curitiba, PR (Brazil)

    2009-07-01

    In this paper, it is presented the development of an innovative and low-cost robotic mobile system to be employed in inspection of pipes. The system is composed of a robot with different sensors which permit to move inside pipes and detect faults as well as incipient faults. The robot is a semiautonomous one, i.e. it can navigate by human tele operation or autonomously one. The autonomous mode uses computer vision techniques and signals from position sensor of the robot to navigating and localizing it. It is showed the mechanical structure of the robot, the overall architecture of the system and preliminary results. (author)

  7. MINAC, portable high energy radiographic inspection system

    International Nuclear Information System (INIS)

    Lapides, M.E.; Schonberg, R.

    1985-01-01

    MINAC, a portable, high energy radiographic source (1) was recognized as a desired inspection device for nuclear generation plants during EPRI-sponsored studies of the late 1970s and rapidly transitioned from proof-of-principle (1978-1980) to field-proven hardware (1981-present date). The equipment has completed its second generation of configuration development (SHRINKAC), that has recently been used in the field for detection of pipe cracks. Important auxiliaries for image data processing and real-time, thick section radiography have been demonstrated in both laboratory and field situations. Finally, a 6 MeV accelerator alternate is in bench test. These significant developments have, and are expected to continue to upgrade the utility of radiographic inspection in power plant practice. This paper describes the development and experience with this modular system during the last three years

  8. An automated system for rail transit infrastructure inspection.

    Science.gov (United States)

    2015-03-01

    This project applied commercial remote sensing and spatial information (CRS&SI) : technologies such as Ground Penetrating Radar (GPR), laser, GIS, and GPS to passenger rail : inspections. An integrated rail inspection system that can be mounted on hi...

  9. A novel inspection system for cosmetic defects

    Science.gov (United States)

    Hazra, S.; Roy, R.; Williams, D.; Aylmore, R.; Hollingdale, D.

    2013-12-01

    The appearance of automotive skin panels creates desirability for a product and differentiates it from the competition. Because of the importance of skin panels, considerable care is taken in minimizing defects such as the 'hollow' defect that occur around door-handle depressions. However, the inspection process is manual, subjective and time-consuming. This paper describes the development of an objective and inspection scheme for the 'hollow' defect. In this inspection process, the geometry of a panel is captured using a structured lighting system. The geometry data is subsequently analyzed by a purpose-built wavelet-based algorithm to identify the location of any defects that may be present and to estimate the perceived severity of the defects without user intervention. This paper describes and critically evaluates the behavior of this physically-based algorithm on an ideal and real geometry and compares its result to an actual audit. The results show that the algorithm is capable of objectively locating and classifying 'hollow' defects in actual panels.

  10. Enhanced InService Inspection system for BWR plant

    International Nuclear Information System (INIS)

    Shouji, Hajime; Kobayashi, Teruo; Nagao, Tetsuya

    1993-01-01

    An enhanced InService Inspection system (ISI) has been developed, consisting of newly designed automated scanners, automated pipe inspection system and a high speed data acquisition/analysis station. This system uses a trackless magnetic crawler type nozzle inspection scanner attached to the nozzle shoulder by magnetic wheels. The automated pipe inspection system consists of an automated scanner, controller and high speed data acquisition station. These advanced automatic inspection systems are very useful for ISI, especially in reducing the radiation exposure and time required. (author)

  11. Calibration of the CCD photonic measuring system for railway inspection

    Science.gov (United States)

    Popov, D. V.; Ryabichenko, R. B.; Krivosheina, E. A.

    2005-08-01

    Increasing of traffic speed is the most important task in Moscow Metro. Requirements for traffic safety grow up simultaneously with the speed increasing. Currently for track inspection in Moscow Metro is used track measurement car has built in 1954. The main drawbacks of this system are absence of automated data processing and low accuracy. Non-contact photonic measurement system (KSIR) is developed for solving this problem. New track inspection car will be built in several months. This car will use two different track inspection systems and car locating subsystem based on track circuit counting. The KSIR consists of four subsystems: rail wear, height and track gauge measurement (BFSM); rail slump measurement (FIP); contact rail measurement (FKR); speed, level and car locating (USI). Currently new subsystem for wheel flange wear (IRK) is developed. The KSIR carry out measurements in real-time mode. The BFSM subsystem contains 4 matrix CCD cameras and 4 infrared stripe illuminators. The FIP subsystem contains 4 line CCD cameras and 4 spot illuminators. The FKR subsystem contains 2 matrix CCD cameras and 2 stripe illuminators. The IRK subsystem contains 2 CCD cameras and 2 stripe illuminators. Each system calibration was carried out for their adjustment. On the first step KSIR obtains data from photonic sensors which is valued in internal measurement units. Due to the calibration on the second step non-contact system converts the data to metric measurement system.

  12. 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...

  13. Development of a remote inspection system for NSSS components

    International Nuclear Information System (INIS)

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

    2004-03-01

    Different operating systems of computerized inspection equipment cause serious problems in graphic user interface between control computers of inspection equipment and remote user computers. Management cost of interface version is very expensive even if the system has been developed. A solution for the interface problems in accessing the remote inspection system is web-based technology. But time-delay problem of web and java, a compiled type S/W that cooperates with web in control computers of inspection equipment is necessary to solve it. This report describes solutions for developing a remote inspection system based on web and java technology

  14. Using CID for internals visual inspection and measurement

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    Solid state sensors for video camera applications, notably the CCD (charge coupled device), tend to be much more compact than conventional tubes and therefore offer advantages in remote viewing applications. A major drawback in the nuclear context, however, is their low tolerance to radiation. Recently, however, Electricite de France and the French company Image Technologie have been working on a solid state vision system using CID (Charge injection device) technology, which is radiation resistant up to 10 5 gamma absorbed dose. The particular application is inspection and measurement of clearances in PWR core guide tubes. The system promises to save outage time by combining metrology with visual inspection - effectively two tools in one. Clearance measurements are made via the screen on the operator's computerized control system using an electronic grid system. Images can then be stored on magnetic tape. The CID camera is located at the lower end of a system of linked rods. The rods connect to a special head at the upper end, which provides fine height adjustment of the tool assembly. (author)

  15. Licensing systems and inspection of nuclear installations

    International Nuclear Information System (INIS)

    1991-01-01

    The first study analysing the regulations governing the licensing and inspection of nuclear installations in OECD countries was published by OECD/NEA in 1980, and revised in 1986. Since then there have been amendments to national regulations on the subject, which have warranted updating of this publication. This new study provides a description of the licensing regulations and practices applied in the twenty OECD countries with provisions in that field. The national systems have been described according to a standard format to make comparisons and research easier. In most cases, the descriptions are supplemented by flow charts illustrating the procedures and specifying the different authorities involved in the licensing procedures [fr

  16. IFSS: The IAEA's inspection field support system

    International Nuclear Information System (INIS)

    Muller, R.; Heinonen, O.J.; Schriefer, D.

    1990-01-01

    Recently, highly automated nuclear facilities with enormous volumes of nuclear material accounting data have come into operation. A few others will become operational shortly. Analysis and verification of the data for safeguards purposes is manageable only with improved computer support in the field. To assist its safeguards inspectors, the IAEA has developed the Inspection Field Support System (IFSS). It allows safeguards inspectors to collect, maintain, analyse, and evaluate inspection data on site at nuclear facilities. Previously, field computer support to safeguards inspectors concentrated on providing measurement instrumentation with data storage, but data analysis capabilities were elementary. Also, generic statistical tools were available to handle data that inspectors could (usually manually) input into a computer. Electronic links between these two directions were rudimentary. IFSS integrates the data required for verification and accounting so that inspectors will be able to devote more time to measurements and to derive conclusions at the site in a more timely manner. The system operates on stationary personal computers as well as on portable ones. Its introduction reflects the IAEA Department of Safeguards determination to further improve operational efficiency. It should be emphasized that IFSS implementation is still under development. Several field installations have been made to obtain practical experience and to determine the system's effectiveness

  17. Realistic modeling of radiation transmission inspection systems

    International Nuclear Information System (INIS)

    Sale, K.E.

    1993-01-01

    We have applied Monte Carlo particle transport methods to assess a proposed neutron transmission inspection system for checked luggage. The geometry of the system and the time, energy and angle dependence of the source have been modeled in detail. A pulsed deuteron beam incident on a thick Be target generates a neutron pulse with a very broad energy spectrum which is detected after passage through the luggage item by a plastic scintillator detector operating in current mode (as opposed to pulse counting mode). The neutron transmission as a function of time information is used to infer the densities of hydrogen, carbon, oxygen and nitrogen in the volume sampled. The measured elemental densities can be compared to signatures for explosives or other contraband. By using such computational modeling it is possible to optimize many aspects of the design of an inspection system without costly and time consuming prototyping experiments or to determine that a proposed scheme will not work. The methods applied here can be used to evaluate neutron or photon schemes based on transmission, scattering or reaction techniques

  18. 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

  19. 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.

  20. 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.

  1. Automobile inspection system based on wireless communication

    Science.gov (United States)

    Miao, Changyun; Ye, Chunqing

    2010-07-01

    This paper aims to research the Automobile Inspection System based on Wireless Communication, and suggests an overall design scheme which uses GPS for speed detection and Bluetooth and GPRS for communication. The communication between PDA and PC was realized by means of GPRS and TCP/IP; and the hardware circuit and software for detection terminal were devised by means of JINOU-3264 Bluetooth Module after analyzing the Bluetooth and its communication protocol. According to the results of debugging test, this system accomplished GPRS based data communication and management as well as the real-time detection on auto safety performance parameters in crash test via PC, whereby the need for mobility and reliability was met and the efficiency and level of detection was improved.

  2. 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)

  3. The application of PLC in 60Co container inspection system

    International Nuclear Information System (INIS)

    Huang Yibin; Xiang Xincheng

    2001-01-01

    The author discusses the interlock technique of 60 Co container inspection system, and introduces the hardware structure and program of interlock control system using PLC. Due to adopting PLC distributed control, the system works stably and reliably. The successful application of PLC in 60 Co container inspection system has some use for reference in nuclear technology field

  4. 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...

  5. Semi-automatic ultrasonic inspection of PWR upper internal immersed components

    International Nuclear Information System (INIS)

    Dombret, P.; Coquette, A.; Cermak, J.; Verspeelt, D.

    1985-01-01

    The present paper describes the characteristics of a semi-automatic ultrasonic inspection system. Components inspected are the so-called flexures, small pins located at the upper part of control rod tube-guide, some of which happened to broke in a few Westinghouse type PWR's. Inspection results and other system capabilities are also mentioned

  6. Pipe robots for internal inspection, non-destructive testing and machining of pipelines

    International Nuclear Information System (INIS)

    Reiss, Alexander

    2016-01-01

    Inspector Systems is a specialist in manufacturing of tethered self-propelled pipe robots for internal inspection, non-destructive testing and machining of pipeline systems. Our industrial sectors, which originates from 30 year experience in the nuclear industry, are Gas and Oil (On-/Offshore, Refineries), Chemical, Petrochemical, Water etc. The pipe robots are able to get inserted through poor access points (e.g. valves) and to pass in bi-directional travelling vertical sections and numerous bends with small arc radius. The paper describes the system concept and performance of the pipe robot technology. A modular construction allows to equip the robots with different operational elements for the respective application.

  7. Machine vision system for remote inspection in hazardous environments

    International Nuclear Information System (INIS)

    Mukherjee, J.K.; Krishna, K.Y.V.; Wadnerkar, A.

    2011-01-01

    Visual Inspection of radioactive components need remote inspection systems for human safety and equipment (CCD imagers) protection from radiation. Elaborate view transport optics is required to deliver images at safe areas while maintaining fidelity of image data. Automation of the system requires robots to operate such equipment. A robotized periscope has been developed to meet the challenge of remote safe viewing and vision based inspection. (author)

  8. An inspection demonstration program/a quality system

    International Nuclear Information System (INIS)

    Cox, L.D.

    1995-01-01

    Mobil relies on tubular manufacturers to consistently supply OCTG which complies with all material requirements of API Specification 5CT. This paper details the Mobil Inspection Demonstration Program; Mobil's method for qualifying ultrasonic inspection systems for use during Mobil receiving inspections. Additionally, the basic fundamentals of the Mobil quality system and acceptance sampling are presented with an emphasis on tracking short-term and long-term supplier performance

  9. Secure Video Surveillance System (SVSS) for unannounced safeguards inspections

    International Nuclear Information System (INIS)

    Galdoz, Erwin G.; Pinkalla, Mark

    2010-01-01

    The Secure Video Surveillance System (SVSS) is a collaborative effort between the U.S. Department of Energy (DOE), Sandia National Laboratories (SNL), and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC). The joint project addresses specific requirements of redundant surveillance systems installed in two South American nuclear facilities as a tool to support unannounced inspections conducted by ABACC and the International Atomic Energy Agency (IAEA). The surveillance covers the critical time (as much as a few hours) between the notification of an inspection and the access of inspectors to the location in facility where surveillance equipment is installed. ABACC and the IAEA currently use the EURATOM Multiple Optical Surveillance System (EMOSS). This outdated system is no longer available or supported by the manufacturer. The current EMOSS system has met the project objective; however, the lack of available replacement parts and system support has made this system unsustainable and has increased the risk of an inoperable system. A new system that utilizes current technology and is maintainable is required to replace the aging EMOSS system. ABACC intends to replace one of the existing ABACC EMOSS systems by the Secure Video Surveillance System. SVSS utilizes commercial off-the shelf (COTS) technologies for all individual components. Sandia National Laboratories supported the system design for SVSS to meet Safeguards requirements, i.e. tamper indication, data authentication, etc. The SVSS consists of two video surveillance cameras linked securely to a data collection unit. The collection unit is capable of retaining historical surveillance data for at least three hours with picture intervals as short as 1sec. Images in .jpg format are available to inspectors using various software review tools. SNL has delivered two SVSS systems for test and evaluation at the ABACC Safeguards Laboratory. An additional 'proto-type' system remains

  10. Periodic inspections of lightning protection systems in intermediate storage facilities of nuclear technological plants

    International Nuclear Information System (INIS)

    Witzel, Andre; Schulz, Olav

    2013-01-01

    Especially for nuclear technological plants, periodic inspections of lightning protection systems are of great importance. This article shows the sequence of maintenance programs using the examples of the intermediate storage facilities of the nuclear technological plants Grohnde and Unterweser as well as the central intermediate storage facility in Gorleben and gives a description of the extensive measures of inspecting the external and internal lightning protection and the global earth termination system.

  11. Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

    Energy Technology Data Exchange (ETDEWEB)

    Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

    1997-07-01

    The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

  12. Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

    International Nuclear Information System (INIS)

    Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

    1997-01-01

    The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

  13. Comparative Study on Urban Planning Inspection System in the UK and China

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    The urban-rural planning inspector system of China is hierarchical supervision over local governments from the Central Government in respect of town and country development. The comparative analysis on planning inspection system of the UK may provide experience in seeking solutions to the problems occurring in the system of China. The planning inspector system of China can be improved in six aspects such as establishing the legal status, setting up the planning inspection agency, completing the personnel management system, enhancing the legal binding force, building the internal and external supervision channel, supplementing the relieve function, and establishing the coordination mechanism of various internal supervisions.

  14. Tire inspection system with shielded x-ray source

    International Nuclear Information System (INIS)

    Heisner, D.N.; Palermo, A. Jr.; Loyer, P.K.

    1976-01-01

    An automated tire inspection system is described which employs a penetrative radiation, such as x-radiation, to inspect the integrity of portions of tires fed sequentially along a feed path through a centering station and into a shielded enclosure where an inspection station is defined. Features of the system include a continuously operating x-ray source movable between inspection and retracted positions, and an x-ray shield for covering the source when it is retracted to permit the doors of the shielded enclosure to be opened without danger from escaping radiation. 19 Claims, 38 Drawing Figures

  15. Outlines of guidelines for the inspection and evaluation of reactor vessel internals

    International Nuclear Information System (INIS)

    Seki, Hiroaki; Kobayashi, Hiroyuki; Nakano, Morihito; Murai, Soutarou; Nomoto, Toshiharu

    2014-01-01

    'The guideline committee for the inspection and evaluation of Reactor Vessel Internals' of JANSI (Japan Nuclear Safety Institute) has been developing many guidelines based on principle which the conservative methodology, and covered both individual inspection method of reactor internals and application of repair methods for reactor internals. In this paper, some aspects of the JANSI-VIP-03 (Guidelines for the inspection and evaluation of Reactor Vessel Internals, revised Dec.2013) which is summary document of the committee activity, are introduced. (author)

  16. Modeling of a remote inspection system for NSSS components

    International Nuclear Information System (INIS)

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

    2003-03-01

    Safety inspection for safety-critical unit of nuclear power plant has been processed using off-line technology. Thus we can not access safety inspection system and inspection data via network such as internet. We are making an on-line control and data access system based on WWW and JAVA technologies which can be used during plant operation to overcome these problems. Users can access inspection systems and inspection data only using web-browser. This report discusses about analysis of the existing remote system and essential techniques such as Web, JAVA, client/server model, and multi-tier model. This report also discusses about a system modeling that we have been developed using these techniques and provides solutions for developing an on-line control and data access system

  17. 14 CFR 125.507 - Fuel tank system inspection program.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Fuel tank system inspection program. 125... Airworthiness and Safety Improvements § 125.507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the certificate holder must submit...

  18. 14 CFR 91.1507 - Fuel tank system inspection program.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Fuel tank system inspection program. 91... Airworthiness and Safety Improvements § 91.1507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the operator must submit to the...

  19. Eliminating NVA Requirements & Improving the Inspection System

    Science.gov (United States)

    2011-01-27

    Wg ISPR Blood Pgm QA JTAC Stan/Eval Formal Joint Comm AAAHC SCI Security Pgm Review Pathologists WII Ed & Dev Inter vent. Servi ces FDA Pubs...his/her tour  Balanced mix of scheduled & no-notice inspections  Units will be inspected for Readiness and Compliance every 24 months  Readiness...a whole  IG Team Chiefs drive team effectiveness, are the most visible direct representatives of MAJCOM CCs & should be selected by CIP or a board

  20. Database management system for large container inspection system

    International Nuclear Information System (INIS)

    Gao Wenhuan; Li Zheng; Kang Kejun; Song Binshan; Liu Fang

    1998-01-01

    Large Container Inspection System (LCIS) based on radiation imaging technology is a powerful tool for the Customs to check the contents inside a large container without opening it. The author has discussed a database application system, as a part of Signal and Image System (SIS), for the LCIS. The basic requirements analysis was done first. Then the selections of computer hardware, operating system, and database management system were made according to the technology and market products circumstance. Based on the above considerations, a database application system with central management and distributed operation features has been implemented

  1. An advanced dispatching technology for large container inspection system

    International Nuclear Information System (INIS)

    Chen Zhiqiang; Zhang Li; Kang Kejun; Gao Wenhuan

    2001-01-01

    The author describes the transmitting and dispatching technology of large container inspection system. It introduces the structure of the double buffer graded pipe lining used in the system. Strategies of queue mechanism and waiting dispatch policy are illustrated

  2. Turnkey Optical Inspection Systems: Getting The Job Done Right

    Science.gov (United States)

    Figler, Burton D.

    1988-05-01

    A turnkey optical inspection system is one for which the vendor, not the customer, assumes the responsibility for ensuring that the system satisfies the customer's needs. This paper presents some of the pitfalls that are encountered in reaching the goal of mutual satisfaction of vendor and customer, based on experience with actual turnkey inspection and measurement systems that have been developed for industrial assembly operations. A "roadmap" is presented for achieving a turnkey system that is satisfactory to both vendor and customer.

  3. Inspection methods for safeguards systems at nuclear facilities

    International Nuclear Information System (INIS)

    Minichino, C.; Richard, E.W.

    1981-01-01

    A project team at Lawrence Livermore National Laboratory has been developing inspection procedures and training materials for the NRC inspectors of safeguards systems at licensed nuclear facilities. This paper describes (1) procedures developed for inspecting for compliance with the Code of Federal Regulations, (2) training materials for safeguards inspectors on technical topics related to safeguards systems, such as computer surety, alarm systems, sampling techniques, and power supplies, and (3) an inspector-oriented methodology for evaluating the overall effectiveness of safeguards systems

  4. Development and deployment of BARC Vessel Inspection System (BARVIS) for TAPS-1 and 2

    International Nuclear Information System (INIS)

    Singh, Jit Pal; Ranjon, R.; Kulkarni, M.P.; Soni, N.L.; Patel, R.J.

    2016-01-01

    As per regulatory requirements, inspection of welds in Reactor Pressure Vessel (RPV) is necessary for further continuing operation of TAPS - 1 and 2. Upper shell longitudinal welds of RPV which were seen as inaccessible up till now have been inspected first time since operation of the reactors by deploying Weld Inspection Manipulator (WIM) in Unit-1 in August 2012. Subsequently Unit-2 and again Unit-1 upper shell welds were inspected with upgraded versions of WIM in Feb 2013 and March 2015 respectively. Inspection of upper shell welds paves the way for more challenging inspection of beltline region welds. These welds are accessible only from Inside Diameter (JD) surface through a narrow annular gap of 25 mm between RPV wall and thermal shield by managing obstructions due to core internals. BARC Vessel Inspection System (BARVIS) for inspection of beltline region welds from inner side of the RPV was designed, manufactured, tested and qualified for sending scanning probes in to the annular gap of 25mm as per RPV engineering drawings and also based on actual gap measured in Unit-2. Annular gap measurement was done in Units-1 before deployment of BARVIS during 25 th Refuelling Outage (RFO) in Unit-1. Contrary to the expectation, the annular gap was found less and inspection of beltline region with BARVIS in Unit-1 could not be done. Finally during RFO in January 2016 of Unit-2, BARVIS has been successfully deployed for beltline region welds inspection. BARVIS mainly consists of manipulator, its operating system and data acquisition system. Data acquisition system and data analysis are not covered in this report. (author)

  5. Ultrasonic inspection experience of steam generator tubes at Ontario Hydro and the TRUSTIE inspection system

    International Nuclear Information System (INIS)

    Choi, E.I.; Jansen, D.

    1998-01-01

    Ontario Hydro have been using ultrasonic test (UT) technique to inspect steam generator (SG) tubes since 1993. The UT technique has higher sensitivity in detecting flaws in SG tubes and can characterize the flaws with higher accuracy. Although an outside contractor was used initially, Ontario Hydro has been using a self-developed system since 1995. The TRUSTIE system (Tiny Rotating UltraSonic Tube Inspection Equipment) was developed by Ontario Hydro Technologies specifically for 12.7 mm outside diameter (OD) tubes, and later expanded to larger tubes. To date TRUSTIE has been used in all of Ontario Hydro's nuclear generating stations inspecting for flaws such as pitting, denting, and cracks at top-of-tubesheet to the U-bend region. (author)

  6. CASTOR - Advanced System for VVER Steam Generator Inspection

    International Nuclear Information System (INIS)

    Mateljak, Petar

    2014-01-01

    From the safety point of view, steam generator is a very important component of a nuclear power plant. Only a thin tube wall prevents leakage of radioactive material from the primary side into the environment. Therefore, it is very important to perform inspections in order to detect pipe damage and apply appropriate corrective actions during outage. Application of the nondestructive examination (NDE) technique, that can locate degradation and measure its size and orientation, is an integral part of nuclear power plant maintenance. The steam generator inspection system is consisted of remotely controlled manipulator, testing instrument and software for data acquisition and analysis. Recently, the inspection systems have evolved to a much higher level of automation, efficiency and reliability resulting in a lower cost and shorter outage time. Electronic components have become smaller and deal with more complex algorithms. These systems are very fast, precise, reliable and easy to handle. The whole inspection, from the planning, examination, data analysis and final report, is now a highly automated process, which makes inspection much easier and more reliable. This paper presents the new generation of INETEC's VVER steam generator inspection system as ultimate solution for steam generator inspection and repair. (author)

  7. Optimal Inspection and Maintenance Strategies for Structural Systems

    DEFF Research Database (Denmark)

    Sommer, A. M.

    The aim of this thesis is to give an overview of conventional and optimal reliability-based inspection and maintenance strategies and to examine for specific structures how the cost can be reduced and/or the safety can be improved by using optimal reliability-based inspection strategies....... For structures with several almost similar components it is suggested that individual inspection strategies should be determined for each component or a group of components based on the reliability of the actual component. The benefit of this procedure is assessed in connection with the structures considered....... Furthermore, in relation to the calculations performed the intention is to modify an existing program for determination of optimal inspection strategies. The main purpose of inspection and maintenance of structural systems is to prevent or delay damage or deterioration to protect people, environment...

  8. Findings of the inspection grading system on industrial radiography

    International Nuclear Information System (INIS)

    Gloria Doloressa

    2011-01-01

    The use of industrial radiography techniques evolve rapidly and widely. Various jobs in industry require the examination of welding techniques / connecting pipes and metal construction. The use of industrial radiography is one type of utilization of nuclear energy must get control so that its use does not cause harmful impacts to worker safety, community, and environment. Regulations is done through inspections, in order to supervise the observance of the terms in the licensing and legislation in the field of nuclear safety. The main purpose of inspection is to ensure the utilization of radiation sources of radiation have been used with. Findings of the inspection is a decline in the performance of licensees in meeting safety requirements. The Grading System to the findings of the inspection needs to be done to improve the effectiveness and efficiency of inspection, and it is expected that the company can improve the management of radiation safety. (author)

  9. Inspection surveys of x-ray inspection systems: results of five years and implications on future management of radiation risks

    International Nuclear Information System (INIS)

    Maharaj, H.P.

    1999-01-01

    Until the mid-1980s, federal inspectors performed radiation surveys annually on individual x-ray inspection systems which were operated for security screening purposes in federal facilities nationwide, and problems identified were corrected. The surveys were undertaken because of perceived high radiation risks and a need to ensure worker and public external exposures were minimized. The x-ray inspection systems are federally regulated under the Radiation Emitting Devices (RED) Act and, initially they were assessed by model type against the design, construction and performance criteria specified in the applicable RED regulations (Schedule II, Part IV) and were found compliant. A subsequent study not only demonstrated a much lower radiation risk attributed to a combination of technological advances in x-ray system design with narrow primary beams, high efficiency detectors and image processing capability, but also stressed the need for proper equipment maintenance and continued education of operators and maintenance personnel. Survey frequency was thus reduced to once every 2-3 years in accordance with a 1993 federal operational standard (Safety Code 29). The radiation protection principles in Safety Code 29 are similar to those of the 1996 International Atomic Energy Agency (IAEA) Basic Safety Standards for the protection against ionizing radiation and the safety of radiation sources. The purpose of this study was to assess inspection-survey data from 1993 through 1997 to elicit guidance toward the future management of radiation risks associated with the operation of such x-ray systems. (author)

  10. Electrical Distribution System Functional Inspection (EDSFI) data base program

    International Nuclear Information System (INIS)

    Gautam, A.

    1993-01-01

    This document describes the organization, installation procedures, and operating instructions for the database computer program containing inspection findings from the US Nuclear Regulatory Commission's (NRC's) Electrical Distribution System Functional Inspections (EDSFIs). The program enables the user to search and sort findings, ascertain trends, and obtain printed reports of the findings. The findings include observations, unresolved issues, or possible deficiencies in the design and implementation of electrical distribution systems in nuclear plants. This database will assist those preparing for electrical inspections, searching for deficiencies in a plant, and determining the corrective actions previously taken for similar deficiencies. This database will be updated as new EDSFIs are completed

  11. Proceedings of the 13. International Workshop on Inspection Practices. 13. International Nuclear Regulatory Inspection Workshop - Appendix of Responses, 17-21 April 2016, Bruges, Belgium

    International Nuclear Information System (INIS)

    2017-01-01

    This appendix provides the complete compilation of responses received to the questionnaire issued in conjunction with the workshop announcements. The responses are provided as received, with changes made only to the formatting. The OECD Nuclear Energy Agency (NEA) Committee on Nuclear Regulatory Activities (CNRA) Working Group on Inspection Practices (WGIP) sponsored the 13. International Workshop on Nuclear Regulatory Inspection Activities. The workshop was hosted by the Bel V and FANC, in Bruges, Belgium on 17 -21 April 2016. The three workshop topics that were addressed were as follows: - Inspection Activities During the Transition from an Operating Reactor to a De-fueled Status with a Commitment to Cease Power Operation; - Inspection of Modifications; - The Inspectors' Role in the Enforcement Process. Each of the respondents was given the following instructions in relation to their response: - Only one response per country is required. If more than one person from your country is participating, please co-ordinate the responses accordingly. - Responses must be provided on separate sheet with clear identification of the questionnaire part and topic. For preparation of the workshop, participants were invited to supply their national inspection approaches used in inspection of events and incidents according to the surveys. Actual issues that were discussed during the workshop were generated by the topic leaders based on the responses submitted by participants with their registration forms. This formats helped to ensure that issues considered most important by the workshop participants were covered during the group discussions

  12. Control system design for robotic underground storage tank inspection systems

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1994-09-01

    Control and data acquisition systems for robotic inspection and surveillance systems used in nuclear waste applications must be capable, versatile, and adaptable to changing conditions. The nuclear waste remediation application is dynamic -- requirements change as public policy is constantly re-examined and refocused, and as technology in this area advances. Control and data acquisition systems must adapt to these changing conditions and be able to accommodate future missions, both predictable and unexpected. This paper describes the control and data acquisition system for the Light Duty Utility Arm (LDUA) System that is being developed for remote surveillance and inspection of underground storage tanks at the Hanford Site and other US Department of Energy (DOE) sites. It is a high-performance system which has been designed for future growth. The priority mission at the Hanford site is to retrieve the waste generated by 50 years of production from its present storage and process it for final disposal. The LDUA will help to gather information about the waste and the tanks it is stored in to better plan and execute the cleanup mission

  13. A survey on inspecting structures using robotic systems

    Directory of Open Access Journals (Sweden)

    Randa Almadhoun

    2016-11-01

    Full Text Available Advancements in robotics and autonomous systems are being deployed nowadays in many application domains such as search and rescue, industrial automation, domestic services and healthcare. These systems are developed to tackle tasks in some of the most challenging, labour intensive and dangerous environments. Inspecting structures (e.g. bridges, buildings, ships, wind turbines and aircrafts is considered a hard task for humans to perform and of critical importance since missing any details could affect the structure’s performance and integrity. Additionally, structure inspection is time and resource intensive and should be performed as efficiently and accurately as possible. Inspecting various structures has been reported in the literature using different robotic platforms to: inspect difficult to reach areas and detect various types of faults and anomalies. Typically, inspection missions involve performing three main tasks: coverage path planning, shape, model or surface reconstruction and the actual inspection of the structure. Coverage path planning ensures the generation of an optimized path that guarantees the complete coverage of the structure of interest in order to gather highly accurate information to be used for shape/model reconstruction. This article aims to provide an overview of the recent work and breakthroughs in the field of coverage path planning and model reconstruction, with focus on 3D reconstruction, for the purpose of robotic inspection.

  14. A remote inspection system for use inside reactor containment vessels

    International Nuclear Information System (INIS)

    Aoki, Toshihiko; Kashiwai, Jun-ichi; Yamamoto, Ikuo; Fukada, Koichi; Yamanaka, Yoshinobu.

    1985-01-01

    The harsh environment in the reactor-containment vesels of pressurized-water reactor nuclear-power plants precludes the possibility of direct circuit inspection; a remote-inspection system is essential. A robot for performing this task must not only be able to withstand the harsh conditions but must also be small and maneuverable enough to function effectively within complex and confined spaces. The article describes a monorail-type remote-inspection robot developed by Mitsubishi Electric to meet these needs, which is now under trial production and testing. (author)

  15. An application of ultrasonic inspection system (INER-SCAN) inspecting generator retaining rings

    International Nuclear Information System (INIS)

    Chen, L.C.; Hwang, S.C.

    1994-01-01

    The performances of the automatic ultrasonic inspecting and imaging system (INER-SCAN) developed by the NDT laboratory of the Institute of Nuclear Energy Research have been enhanced and much more improved to commercial level. With appropriate rearrangements of software libraries, it is used to inspect generator retaining rings which are critical structural rotor components that support the end-turn regions of the rotor wingings against centrifugal forces. The use of the INER-SCAN provides distinct advantages over other systems in terms of the reliability of inspection and the flexibility of system performance modifications. The INER-SCAN system assists users to select and modify ultrasonic parameters under computer-aided environment. In addition, the INER-SCAN system contains the necessary software functions to image the ultrasonic data (A-SCAN, B-SCAN, B'-SCAN, C-SCAN). The use of the imaging system makes it quite easy to evaluate various test parameters and their effects on the discrimination between geometric and IGSCC reflectors. Through experimental test, it is recognized that the system has powerful detectable capability which can find 0.2mm-depth slight scratch on the inner surface of retaining rings. This system can also be used on different generator retaining rings (different in terms of hidden design features) without the need for access to the dimension of retaining ring

  16. Development of Remote Inspection Systems with the Java Applet

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2005-07-01

    The world wide web and java are powerful networking technologies on the internet. An applet is a program written in the java programming language that can be included in an HTML page, much in the same way as an image is included. When we use a Java technology-enabled browser to view a page that contains an applet, the applet code is transferred to a client's system and executed by the browser's Java Virtual Machine (JVM). We have developed two remote inspection systems for a reactor wall inspection and guide tube spilt pin inspection based on the java and traditional programming language. The java is used on a GUI(graphic user interface) and the traditional visual C++ programming language is used to control the inspection equipments.

  17. Development of Remote Inspection Systems with the Java Applet

    International Nuclear Information System (INIS)

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

    2005-01-01

    The world wide web and java are powerful networking technologies on the internet. An applet is a program written in the java programming language that can be included in an HTML page, much in the same way as an image is included. When we use a Java technology-enabled browser to view a page that contains an applet, the applet code is transferred to a client's system and executed by the browser's Java Virtual Machine (JVM). We have developed two remote inspection systems for a reactor wall inspection and guide tube spilt pin inspection based on the java and traditional programming language. The java is used on a GUI(graphic user interface) and the traditional visual C++ programming language is used to control the inspection equipments

  18. Proceedings of the 13. International Workshop on Inspection Practices. 13. International Nuclear Regulatory Inspection Workshop, 17-21 April 2016, Bruges, Belgium

    International Nuclear Information System (INIS)

    Bens, Jan; De Boeck, Benoit; Wertelaers, An; Van Haesendonck, Michel; Barras, Pierre; Leblanc, Alexandre; Regan, Christopher; Smith, Paul; Kupila, Jukka; Crespo, Julio; Meskens, Gaston; Schneider, Matthias

    2017-01-01

    The main purpose of the workshop was to provide a forum for information exchange on the regulatory inspection activities. Participants had the opportunity to meet with their counterparts from other countries and organisations to discuss current and future issues on the selected topics. They developed conclusions regarding these issues and identified methods that may help to improve their own inspection programmes. The CNRA believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established working groups and groups of experts in specialised topics. The Working Group on Inspection Practices (WGIP) was formed in 1990 with the mandate '...to concentrate on the conduct of inspections and how the effectiveness of inspections could be evaluated..'. The WGIP facilitates the exchange of information and experience related to regulatory safety inspections between CNRA member countries. These proceedings cover the 13. International Nuclear Regulatory Inspection Workshop held by WGIP on regulatory inspection activities. This workshop, which is the 13. in a series, along with many other activities performed by the working group, is directed towards this goal. The consensus from participants at previous workshops noted that the value of meeting with people from other inspection organisations was one of the most important achievements. The focus of this workshop was on experience gained from regulatory inspection activities in three areas: - experience from the inspection activities during the transition from an operating reactor to a de-fueled status with a commitment to permanently cease power operations; - inspection of modifications; - the inspectors' role in the enforcement process. As part of the registration, participants were asked to respond to a questionnaire describing practices within their own countries on these topics

  19. 33 CFR 157.148 - COW system: Evidence for inspections.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false COW system: Evidence for... CARRYING OIL IN BULK Crude Oil Washing (COW) System on Tank Vessels Inspections § 157.148 COW system... inspector evidence that the COW system has been installed in accordance with the plans accepted under § 157...

  20. 49 CFR 180.416 - Discharge system inspection and maintenance program for cargo tanks transporting liquefied...

    Science.gov (United States)

    2010-10-01

    ... section. (v) Stainless steel flexible connectors with damaged reinforcement braid. (vi) Internal self... program for cargo tanks transporting liquefied compressed gases. 180.416 Section 180.416 Transportation... PACKAGINGS Qualification and Maintenance of Cargo Tanks § 180.416 Discharge system inspection and maintenance...

  1. MC ampersand A policy issues for international inspections at DOE nuclear facilities

    International Nuclear Information System (INIS)

    Crawford, D.W.; Zack, N.R.

    1994-01-01

    Recent initiatives and executive decisions within the US have included an offer to place certain special nuclear materials from the former weapons stockpile under international safeguards inspections. The nuclear materials at issue are excess materials; other materials characterized as strategic reserve will not be subject to these international activities. Current Department of Energy requirements and procedures to account for and control these nuclear materials may need to be modified to accommodate these inspections. Safeguards issues, such as physical inventory frequency and verification requirements, may rise from the collateral safeguards activities in support of both domestic and international safeguards. This paper will discuss Office of Safeguards and Security policy and views on these international inspection activities at former nuclear weapons facilities, including implications for current domestic safeguards approaches currently implemented at these facilities

  2. Implementation of a Quality Management System in regulatory inspection activities

    International Nuclear Information System (INIS)

    Pires do Rio, Monica; Ferreira, Paulo Roberto; Cunha, Paulo G. da; Acar, Maria Elizabeth

    2005-01-01

    The Institute for Radioprotection and Dosimetry - IRD -, of the Brazilian National Nuclear Energy Commission, CNEN, started in 2001, the implementation of a quality management system (SGQ), in the inspection, testing and calibration activities. The SGQ was an institutional guideline and is inserted in a larger system of management of the IRD started in 1999, with the adoption of the National Quality Award criteria - PNQ, within the Project for Excellence in Technological Research of Associacao Brasileira das Instituicoes de Pesquisas Tecnologicas - ABIPTI (Brazilian Association of Technological Research institutions). The proposed quality management system and adopted at the IRD was developed and implemented in accordance with the requirements of NBR ISO/IEC 17025 - General requirements for the competence of testing and calibration laboratories, and ISO/IEC 17020 - General criteria for operation of various types of bodies performing inspections. For regulatory inspection activities, the quality system was implemented on three program inspection services of radiological protection led, respectively, by clinics and hospitals that operate radiotherapy services; industries that use nuclear gauges in their control or productive processes and power reactor operators (CNAAA) - just the environmental part. It was formed a pioneering team of inspectors for standardizing the processes, procedures and starting the implementation of the system in the areas. This work describes the implementation process steps, including difficulties, learning and advantages of the adoption of a quality management system in inspection activities

  3. Full-scale testing of waste package inspection system

    International Nuclear Information System (INIS)

    Yagi, T.; Kuribayashi, H.; Moriya, Y.; Fujisawa, H.; Takebayashi, N.

    1989-01-01

    In land disposal of low-level radioactive waste (LLW) in Japan, it is legally required that the waste packages to be disposed of be inspected for conformance to applicable technical regulations prior to shipment from each existing power station. JGC has constructed a fully automatic waste package inspection system for the purpose of obtaining the required design data and proving the performance of the system. This system consists of three inspection units (for visual inspection, surface contamination/dose rate measurement and radioactivity/weight measurement), a labelling unit, a centralized control unit and a drum handling unit. The outstanding features of the system are as follows: The equipment and components are modularized and designed to be of the most compact size and the quality control functions are performed by an advanced centralized control system. The authors discuss how, as a result of the full-scale testing, it has been confirmed that this system satisfies all the performance requirements for the inspection of disposal packages

  4. 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

  5. 75 FR 38765 - Domestic Origin Verification System Questionnaire and Regulations Governing Inspection and...

    Science.gov (United States)

    2010-07-06

    ..., facility assessment services, certifications of quantity and quality, import product inspections, and... control number. These include export certification, inspection of section 8e import products, and...] Domestic Origin Verification System Questionnaire and Regulations Governing Inspection and Certification of...

  6. Robotized system for in-pipe inspection using pressure tolerant electronics technique

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Ramon R; Hsu, Liu; Peixoto, Alessandro J; Gomes, Luiz P.C.S. [Coordenacao dos Programas de Pos-graduacao de Engenharia (UFRJ/COPPE), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica. Grupo de Simulacao e Controle em Automacao e Robotica (GSCAR)]. E-mail: ramon, liu, jacoud, lpgomes@coep.ufrj.br; Reis, Ney R.S. dos [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil). Centro de Pesquisas. Lab. de Robotica]. E-mail: salvireis@cenpes.petrobras.com.br

    2003-07-01

    This paper reports the development and experimental evaluation of a robotized system devised to perform two kinds of measurements inside a pipeline: the thickness of the internal wall painting layer and the internal radius. The thickness measurement allows the inspection of the painting layer quality and by measuring several radii it is possible to estimate the pipeline transversal section shape. The proposed scheme is shown to yield very satisfactory results on an actual 14'' (inches) pipeline in a real site. (author)

  7. The JET high temperature in-vessel inspection system

    International Nuclear Information System (INIS)

    Businaro, T.; Cusack, R.; Calbiati, L.; Raimondi, T.

    1989-01-01

    The JET In-vessel Inspection System (IVIS) has been enhanced for operation under the following nominal conditions: vacuum vessel at 350 degC; vacuum vessel evacuated (∼10 -9 mbar); radiation dose during D-T phase 10 rads. The target resolution of the pictures is 2 mm at 5 m distance and tests on radiation resistance of the IVIS system are being carried out. Since June 1988, the new system is installed in the JET machine and the first inspections of the intire vessel at 250 degC have been satisfactory done. (author). 3 refs.; 6 figs.; 1 tab

  8. Information managing in 60Co container inspection system

    International Nuclear Information System (INIS)

    Wu Zhifang; Gu Bohua; Zhou Liye; An Jigang; Liu Yisi

    1998-01-01

    The design, maintenance and realization of information managing database in 60 Co container inspection system made by INET of Tsinghua University is introduced. The technique of Open Database Connectivity (ODBC) is adopted to develop a general format database including text and graphic information. The database application is developed with Visual C ++ 5.0 programming language to run in 32-bit Windows operation system. It conforms to Client/Server model and supports network communication. It works very well in the laboratory emulator of 60 Co container inspection system

  9. A Ship Cargo Hold Inspection Approach Using Laser Vision Systems

    OpenAIRE

    SHEN Yang; ZHAO Ning; LIU Haiwei; MI Chao

    2013-01-01

    Our paper represents a vision system based on the laser measurement system (LMS) for bulk ship inspection. The LMS scanner with 2-axis servo system is installed on the ship loader to build the shape of the ship. Then, a group of real-time image processing algorithms are implemented to compute the shape of the cargo hold, the inclination angle of the ship and the relative position between the ship loader and the cargo hold. Based on those computed inspection data of the ship, the ship loader c...

  10. Automated ultrasonic inspection system for nuclear power stations

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The automated system of ultrasonic inspection which was used to conduct weld inspections of the complex primary system of the Borselle PWR station is described. It relies upon mechanically traversing purpose designed multi-crystal ultrasonic probes along the welds. A number of probes are switched sequentially to provide a continuous scan. A typical scan rate of 120 scan/sec is achieved by a multiplexer capable of switching transmitter and receiver individually. The system has wide applications in other industries. (U.K.)

  11. Development of machine vision system for PHWR fuel pellet inspection

    Energy Technology Data Exchange (ETDEWEB)

    Kamalesh Kumar, B.; Reddy, K.S.; Lakshminarayana, A.; Sastry, V.S.; Ramana Rao, A.V. [Nuclear Fuel Complex, Hyderabad, Andhra Pradesh (India); Joshi, M.; Deshpande, P.; Navathe, C.P.; Jayaraj, R.N. [Raja Ramanna Centre for Advanced Technology, Indore, Madhya Pradesh (India)

    2008-07-01

    Nuclear Fuel Complex, a constituent of Department of Atomic Energy; India is responsible for manufacturing nuclear fuel in India . Over a million Uranium-di-oxide pellets fabricated per annum need visual inspection . In order to overcome the limitations of human based visual inspection, NFC has undertaken the development of machine vision system. The development involved designing various subsystems viz. mechanical and control subsystem for handling and rotation of fuel pellets, lighting subsystem for illumination, image acquisition system, and image processing system and integration. This paper brings out details of various subsystems and results obtained from the trials conducted. (author)

  12. A novel AOI system for OLED panel inspection

    International Nuclear Information System (INIS)

    Perng, D B; Chen, Y C; Lee, M K

    2005-01-01

    Organic light emitting diode (OLED) technology uses substances that emit red, green, blue or white light. An OLED panel consists of stacks of several thin layers of different materials, as such it is not easy to inspect the common OLED defects. In this paper, an autooptical inspection (AOI) system which can detect such defects effectively and robustly was proposed and developed. The proposed system can also identify, in which layer the defect occurred. Meanwhile, a moving mechanism coupled with a lighting mechanism was proposed and implemented for grabbing clear images. The proposed AOI system would provide great help in improving the OLED production process and the quality control process

  13. NELIS - a Neutron Inspection System for Detection of Illicit Drugs

    International Nuclear Information System (INIS)

    Barzilov, Alexander P.; Womble, Phillip C.; Vourvopoulos, George

    2003-01-01

    NELIS (Neutron ELemental Inspection System) is currently being developed to inspect cargo pallets for illicit drugs. NELIS must be used in conjunction with an x-ray imaging system to optimize the inspection capabilities at ports of entry. Pulsed fast-thermal neutron analysis is utilized to measure the major and minor chemical elements in a non-destructive and non-intrusive manner. Fourteen-MeV neutrons produced with a pulsed d-T neutron generator are the interrogating particles. NELIS analyzes the characteristic gamma rays emitted from the object that are produced by nuclear reactions from fast and thermal neutrons. These gamma rays have different energies for each chemical element, and act as their fingerprints. Since the elemental composition of illicit drugs is quite different from that of innocuous materials, drugs hidden in pallets are identified through the comparison of expected and measured elemental composition and ratios. Results of tests of the system will be discussed

  14. Apparatus for integrated fuel assembly inspection system

    International Nuclear Information System (INIS)

    Ahmed, H.J.; Burchill, S.R.

    1988-01-01

    In a fuel assembly inspection apparatus, the combination is described comprising: (a) an elongated fixture mounted in a stationary upright position; (b) upper means mounted to an upper portion of the fixture and lower means mounted adjacent to a lower portion of the fixture, the upper and lower means being disposed outwardly from a side of the fixture for supporting a nuclear fuel assembly therebetween and extending along the side of the fixture; (c) a bottom carriage having a central opening adapted to receive the fuel assembly therethrough when supported between the upper and lower means such that the bottom carriage being connected only to, and extending in cantilever fashion outwardly from, the side of the fixture for generally vertical movement along the side of the fixture and along the fuel assembly extending along the side of the fixture; (d) drive means for selectively moving the bottom carriage; and (e) means disposed on the bottom carriage for measuring the envelop, of the fuel assembly when the bottom carriage is moved to and stationed at selected axial positions along the fuel assembly

  15. Risk-based inspection and maintenance systems for steam turbines

    International Nuclear Information System (INIS)

    Fujiyama, Kazunari; Nagai, Satoshi; Akikuni, Yasunari; Fujiwara, Toshihiro; Furuya, Kenichiro; Matsumoto, Shigeru; Takagi, Kentaro; Kawabata, Taro

    2004-01-01

    The risk-based maintenance (RBM) system has been developed for steam turbine plants coupled with the quick inspection systems. The RBM system utilizes the field failure and inspection database accumulated over 30 years. The failure modes are determined for each component of steam turbines and the failure scenarios are described as event trees. The probability of failure is expressed in the form of unreliability functions of operation hours or start-up cycles through the cumulative hazard function method. The posterior unreliability is derived from the field data analysis according to the inspection information. Quick inspection can be conducted using air-cooled borescope and heat resistant ultrasonic sensors even if the turbine is not cooled down sufficiently. Another inspection information comes from degradation and damage measurement. The probabilistic life assessment using structural analysis and statistical material properties, the latter is estimated from hardness measurement, replica observation and embrittlement measurement. The risk function is calculated as the sum product of unreliability functions and expected monetary loss as the consequence of failure along event trees. The optimum maintenance plan is determined among simulated scenarios described through component breakdown trees, life cycle event trees and risk functions. Those methods are effective for total condition assessment and economical maintenance for operating plants

  16. 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.

  17. 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

  18. IEC-based neutron generator for security inspection system

    International Nuclear Information System (INIS)

    Miley, G.H.; Wu, L.; Kim, H.J.

    2005-01-01

    Use of a combined X-ray and neutron source for security inspections based on Inertial Electrostatic Confinement (IEC) fusion is discussed. Current inspection systems typically use X-ray techniques, but thermal neutron analysis (TNA) and fast neutron analysis (FNA), allow expanded detection of certain types of explosives. The integrated unit proposed here uses three separate IEC sources producing 14 and 2.45 MeV neutrons plus soft X-rays. This combination allows multiple detection methods with the composite signal analysis being done by a fuzzy logic system, significantly reducing false signals. (author)

  19. Periodic inspection for safety of CANDU heat transport piping systems

    International Nuclear Information System (INIS)

    Ellyin, F.

    1979-10-01

    Periodic inspection of heat transport and emergency core cooling piping systems is intended to maintain an adequate level of safety throughout the life of the plant, and to protect plant personnel and the public from the consequences of a failure and release of fission products. This report outlines a rational approach to the periodic inspection based on a fully probabilistic model. It demonstrates the methodology based on theoretical treatment and experimental data whereby the strength of a pressurized pipe or vessel containing a defect could be evaluated. It also shows how the extension of the defect at various lifetimes could be predicted. These relationships are prerequisite for the probabilistic formulation and analysis for the periodic inspection of piping systems

  20. Autonomous navigation system for mobile robots of inspection

    International Nuclear Information System (INIS)

    Angulo S, P.; Segovia de los Rios, A.

    2005-01-01

    One of the goals in robotics is the human personnel's protection that work in dangerous areas or of difficult access, such it is the case of the nuclear industry where exist areas that, for their own nature, they are inaccessible for the human personnel, such as areas with high radiation level or high temperatures; it is in these cases where it is indispensable the use of an inspection system that is able to carry out a sampling of the area in order to determine if this areas can be accessible for the human personnel. In this situation it is possible to use an inspection system based on a mobile robot, of preference of autonomous navigation, for the realization of such inspection avoiding by this way the human personnel's exposure. The present work proposes a model of autonomous navigation for a mobile robot Pioneer 2-D Xe based on the algorithm of wall following using the paradigm of fuzzy logic. (Author)

  1. Optimal Inspection and Repair Strategies for Structural Systems

    DEFF Research Database (Denmark)

    Sommer, A. M.; Nowak, A. S.; Thoft-Christensen, Palle

    1992-01-01

    and a design variable as optimization variables. A model for estimating the total expected costs for structural systems is given including the costs associated with the loss of individual structural members as well as the costs associated with the loss of at least one element of a particular group......A model for reliability-based repair and maintenance strategies of structural systems is described. The total expected costs in the lifetime of the structure are minimized with the number of inspections, the number and positions of the inspected points, the inspection efforts, the repair criteria...... of structural members and the costs associated with the simultaneous loss of all members of a specific group of structural members. The approach is based on the pre-posteriori analysis from the classical decision theory. Special emphasis is given to the problem of selecting the number of points in the structure...

  2. Development of the pellet grinding and inspection system

    International Nuclear Information System (INIS)

    Yamaguchi, Toshihiro; Kawasaki, Takao; Inui, Toshihiko; Yamada, Hiroyuki.

    1996-01-01

    The pellet grinding and inspection system is the facility of producing the MOX fuel for FBRs, and it was delivered in March, 1996 to the No. 3 Development Office of the plutonium fuel shop in Tokai of Power Reactor and Nuclear Fuel Development Corporation. This facility realized the high speed processing using the compact facility by combining the grinding of pellets, the inspection of outer density and appearance, the rationalization of the facility and the high performance automation equipment. The production processes of MOX comprise the processes of powder, sinter, finish and inspection, fabrication and assembling. The requirement for developing these facilities is shown. The features of this pellet grinding and inspection system are the compact facility by the combination of functions, high speed processing, the reduction of holdup in processes and the improvement of maintenance. These features are explained. The main components are simple sorting equipment, grinder, grinding dust recovering equipment, outside diameter and density sorting equipment and appearance inspection equipment. The constitution and the main functions of the control facility are described. The operational process is explained. (K.I.)

  3. 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).

  4. An approach to software quality assurance for robotic inspection systems

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1993-10-01

    Software quality assurance (SQA) for robotic systems used in nuclear waste applications is vital to ensure that the systems operate safely and reliably and pose a minimum risk to humans and the environment. This paper describes the SQA approach for the control and data acquisition system for a robotic system being developed for remote surveillance and inspection of underground storage tanks (UST) at the Hanford Site

  5. Application of eddy current inspection to the Inconel weld of BWR internals

    International Nuclear Information System (INIS)

    Machida, Eiji; Yusa, Noritaka

    2004-01-01

    In order to definite the basic specifications of application of ECT (Eddy Current Test) to Inconel weld of BWR internals, the inspection and numerical analysis were carried out. The characteristics of the existing ECT probe were studied by making sample as same as CRD stud tube, measuring the relative permeability and electric conductivity of Inconel and alloy and evaluating ECT probe. On the basis of the results obtained, the basic specifications were determined and a new eddy current probe for inspection was designed and produced. The new ECT probe was able to detect small notch in Inconel weld, to classify the defects by eddy current inspection signal and sizing the length and depth. It is concluded that the new ECT probe is able to apply the Inconel weld of BWR internals. (S.Y.)

  6. The Expert System Application For Inspection Of The Power Plants

    International Nuclear Information System (INIS)

    Josowidagdo, L.

    1997-01-01

    This paper describes the application of expert system to evaluate and consider the problem encountered in this fields are complex and time consuming. As as example several factors affecting system voltage selections are load magnitude, distance from the main power supply, safety, standards, cost of utilization and service system equipment, and future load growth. The inspection deal with interactions between alternatives, uncertainties, and important non financial parameter. Several complex problems are multiple objective functions, multiple constraints, complex system interactions, the need for accuracy, the need for trade off, optimization, and coordination of the decision making process. ASDEP is one of the expert system for electric power plant design that describe the application of the artificial intelligence to design of a power plan's electrical auxiliary system. In this circumstance this paper will elaborate another aspect for using the expert system in the inspection

  7. Remote Inspection Techniques for Reactor Internals of Liquid Metal Reactor by using Ultrasonic Waveguide Sensor

    International Nuclear Information System (INIS)

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

    2006-02-01

    The primary components such as a reactor core, heat exchangers, pumps and internal structures 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 and continuous monitoring as major in-service inspection (ISI) methods of reactor internal structures. Reactor core and internal structures of LMR can not be visually examined due to an opaque liquid sodium. The under-sodium viewing and remote inspection techniques by using an ultrasonic wave should be applied for the in-service inspection of reactor internals. The remote inspection techniques using ultrasonic wave have been developed and applied for the visualization and ISI of reactor internals. The under sodium viewing technique has a limitation for the application of LMR due to the high temperature and irradiation environment. In this study, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium viewing and remote inspection. The Lamb wave propagation of a waveguide sensor has been analyzed and the zero-order antisymmetric A 0 plate wave was selected as the application mode of the sensor. The A 0 plate wave can be propagated in the dispersive low frequency range by using a liquid wedge clamped to the waveguide. A new technique is presented which is capable of steering the radiation beam angle of a waveguide sensor without a mechanical movement of the sensor assembly. The steering function of the ultrasonic radiation beam can be achieved by a frequency tuning method of the excitation pulse in the dispersive range of the A 0 mode. The technique provides an opportunity to overcome the scanning limitation of a waveguide sensor. The beam steering function has been evaluated by an experimental verification. The ultrasonic C-scanning experiments are performed in water and the feasibility of the ultrasonic waveguide sensor has been verified. The various remote inspection

  8. Safety inspections in construction sites: A systems thinking perspective.

    Science.gov (United States)

    Saurin, Tarcisio Abreu

    2016-08-01

    Although safety inspections carried out by government officers are important for the prevention of accidents, there is little in-depth knowledge on their outcomes and processes leading to these. This research deals with this gap by using systems thinking (ST) as a lens for obtaining insights into safety inspections in construction sites. Thirteen case studies of sites with prohibited works were carried out, discussing how four attributes of ST were used in the inspections. The studies were undertaken over 6 years, and sources of evidence involved participant observation, direct observations, analysis of documents and interviews. Two complementary ways for obtaining insights into inspections, based on ST, were identified: (i) the design of the study itself needs to be in line with ST; and (ii) data collection and analysis should focus on the agents involved in the inspections, the interactions between agents, the constraints and opportunities faced by agents, the outcomes of interactions, and the recommendations for influencing interactions. Copyright © 2015 Elsevier Ltd. All rights reserved.

  9. Smart Infrared Inspection System Field Operational Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Siekmann, Adam [ORNL; Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL

    2011-06-01

    The Smart InfraRed Inspection System (SIRIS) is a tool designed to assist inspectors in determining which vehicles passing through the SIRIS system are in need of further inspection by measuring the thermal data from the wheel components. As a vehicle enters the system, infrared cameras on the road measure temperatures of the brakes, tires, and wheel bearings on both wheel ends of commercial motor vehicles (CMVs) in motion. This thermal data is then presented to enforcement personal inside of the inspection station on a user friendly interface. Vehicles that are suspected to have a violation are automatically alerted to the enforcement staff. The main goal of the SIRIS field operational test (FOT) was to collect data to evaluate the performance of the prototype system and determine the viability of such a system being used for commercial motor vehicle enforcement. From March 2010 to September 2010, ORNL facilitated the SIRIS FOT at the Greene County Inspection Station (IS) in Greeneville, Tennessee. During the course of the FOT, 413 CMVs were given a North American Standard (NAS) Level-1 inspection. Of those 413 CMVs, 384 were subjected to a SIRIS screening. A total of 36 (9.38%) of the vehicles were flagged by SIRIS as having one or more thermal issues; with brakes issues making up 33 (91.67%) of those. Of the 36 vehicles flagged as having thermal issues, 31 (86.11%) were found to have a violation and 30 (83.33%) of those vehicles were placed out-of-service (OOS). Overall the enforcement personnel who have used SIRIS for screening purposes have had positive feedback on the potential of SIRIS. With improvements in detection algorithms and stability, the system will be beneficial to the CMV enforcement community and increase overall trooper productivity by accurately identifying a higher percentage of CMVs to be placed OOS with minimal error. No future evaluation of SIRIS has been deemed necessary and specifications for a production system will soon be drafted.

  10. Eddy current system for inspection of train hollow axles

    Energy Technology Data Exchange (ETDEWEB)

    Chady, Tomasz; Psuj, Grzegorz; Sikora, Ryszard; Kowalczyk, Jacek; Spychalski, Ireneusz [Department of Electrical and Computer Engineering, Faculty of Electrical Engineering, West Pomeranian University of Technology, Szczecin (Poland)

    2014-02-18

    The structural integrity of wheelsets used in rolling stock is of great importance to the safety. In this paper, electromagnetic system with an eddy current transducer suitable for the inspection of hollow axles have been presented. The transducer was developed to detect surface braking defects having depth not smaller than 0.5 mm. Ultrasound technique can be utilized to inspect the whole axle, but it is not sufficiently sensitive to shallow defects located close to the surface. Therefore, the electromagnetic technique is proposed to detect surface breaking cracks that cannot be detected by ultrasonic technique.

  11. P-scan, a new system for ultrasonic weld inspection

    International Nuclear Information System (INIS)

    Lund, S.A.; Iversen, S.E.; Holst, H.

    1978-01-01

    The P-scan method is explained. It is described how the new P-scan system improves the ultrasonic method by adding means for visualization, data storage and documentation. Three different scanners are described: One designed for manual operation, another for automatic operation and a third for semiautomatic operation. The p'scan image of an ultrasonically examined test plate is presented and discussed. The variable Display Level (i.e. the inspection sensitivity) facility is described. The main advantage of this facility is the fact that the level can be varied at any time after the inspection. (orig.) [de

  12. Plant inspection tours with mobile data logging system

    International Nuclear Information System (INIS)

    Roesser, U.

    2006-01-01

    The MDE Mobile Data Logging System has been introduced in a number of German power plants for efficient logging, evaluation, and quality-assured documentation of data recorded on plant inspection tours by means of pocket PCs instead of slips of paper. It will be installed in other nuclear power plants in the near future. The MDE system is composed of the pocket PCs for logging data during plant inspection tours, the associated docking stations installed in the respective areas of application, one PC or, if necessary, several PCs with the appropriate user software, and the associated network links. To install the software in the power plant, lists of rooms and measurement stations as well as other positions on an inspection course are transmitted to the MDE system. When the system has been commissioned, inspection tours are planned in accordance with past experience and optimized in the computer. User experience is taken into account in program updates. New functions improve user comfort and ease of evaluation. Additions to the MDE software, and applications in other areas, are tentatively planned and will be implemented as the need arises. (orig.)

  13. Graphical means for inspecting qualitative models of system behaviour

    NARCIS (Netherlands)

    Bouwer, A.; Bredeweg, B.

    2010-01-01

    This article presents the design and evaluation of a tool for inspecting conceptual models of system behaviour. The basis for this research is the Garp framework for qualitative simulation. This framework includes modelling primitives, such as entities, quantities and causal dependencies, which are

  14. Licensing systems and inspection of nuclear installations

    International Nuclear Information System (INIS)

    1986-01-01

    The systems of each country member of the OECD is described according to a plan standardised to the extent possible, so as to facilitate comparison between the National systems. In most cases, the descriptions are supplemented by flow charts illustrating the steps in the licensing procedure and the intervention of the various bodies concerned

  15. Control system for a multi-joint inspection robot

    International Nuclear Information System (INIS)

    Asano, K.

    1984-01-01

    Remote systems, in which a human operator in a safe zone determines pertinent circumstances and makes decisions on work procedures, while a robot does direct work in hazardous environments, have been becoming more and more important in accordance with the increase in nuclear facilities. In such remote systems, to perform tasks which are merely ambiguously defined beforehand, it is very important that the systems have the ability to execute desired tasks easily and immediately without any programming or teaching work on the spot. A control system, named Self Approach System (SAS), for a multi-joint inspection robot has been developed as a key component in a remote inspection system for use in physically difficult or dangerous environments. It has 8 joints and 17 degrees-of-freedom and was designed taking many of the above points into account. This paper describes SAS details

  16. Inspection system for Zircaloy clad fuel rods

    International Nuclear Information System (INIS)

    Yancey, M.E.; Porter, E.H.; Hansen, H.R.

    1975-10-01

    A description is presented of the design, development, and performance of a remote scanning system for nondestructive examination of fuel rods. Characteristics that are examined include microcracking of fuel rod cladding, fuel-cladding interaction, cladding thickness, fuel rod diameter variation, and fuel rod bowing. Microcracking of both the inner and outer fuel rod surfaces and variations in wall thickness are detected by using a pulsed eddy current technique developed by Argonne National Laboratory (ANL). Fuel rod diameter variation and fuel rod bowing are detected by using two linear variable differential transformers (LVDTs) and a signal conditioning system. The system's mechanical features include variable scanning speeds, a precision indexing system, and a servomechanism to maintain proper probe alignment. Initial results indicate that the system is a very useful mechanism for characterizing irradiated fuel rods

  17. Guiding device for a manipulator mast for internal inspection of a reactor pressure vessel

    International Nuclear Information System (INIS)

    Seifert, W.; Schlueter, H.

    1977-01-01

    A remote-controlled supporting device centering a manipulator mast is described which is mounted and operated above a reactor pressure vessel under water in such a way that rotations and vertical movements necessary for the internal inspection of the pressure vessel remain possible. (RW) [de

  18. Development of In-situation radioactivity Inspection system

    International Nuclear Information System (INIS)

    Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang; Park, Jungkyun

    2015-01-01

    Many Korean people worry about radioactive contamination of Japanese and Korean marine products. 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. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. 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 will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection

  19. Development of In-situation radioactivity Inspection system

    Energy Technology Data Exchange (ETDEWEB)

    Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of); Park, Jungkyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Many Korean people worry about radioactive contamination of Japanese and Korean marine products. 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. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. 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 will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection.

  20. Fast coincidence counting with active inspection systems

    Science.gov (United States)

    Mullens, J. A.; Neal, J. S.; Hausladen, P. A.; Pozzi, S. A.; Mihalczo, J. T.

    2005-12-01

    This paper describes 2nd and 3rd order time coincidence distributions measurements with a GHz processor that synchronously samples 5 or 10 channels of data from radiation detectors near fissile material. On-line, time coincidence distributions are measured between detectors or between detectors and an external stimulating source. Detector-to-detector correlations are useful for passive measurements also. The processor also measures the number of times n pulses occur in a selectable time window and compares this multiplet distribution to a Poisson distribution as a method of determining the occurrence of fission. The detectors respond to radiation emitted in the fission process induced internally by inherent sources or by external sources such as LINACS, DT generators either pulsed or steady state with alpha detectors, etc. Data can be acquired from prompt emission during the source pulse, prompt emissions immediately after the source pulse, or delayed emissions between source pulses. These types of time coincidence measurements (occurring on the time scale of the fission chain multiplication processes for nuclear weapons grade U and Pu) are useful for determining the presence of these fissile materials and quantifying the amount, and are useful for counter terrorism and nuclear material control and accountability. This paper presents the results for a variety of measurements.

  1. Fast coincidence counting with active inspection systems

    International Nuclear Information System (INIS)

    Mullens, J.A.; Neal, J.S.; Hausladen, P.A.; Pozzi, S.A.; Mihalczo, J.T.

    2005-01-01

    This paper describes 2nd and 3rd order time coincidence distributions measurements with a GHz processor that synchronously samples 5 or 10 channels of data from radiation detectors near fissile material. On-line, time coincidence distributions are measured between detectors or between detectors and an external stimulating source. Detector-to-detector correlations are useful for passive measurements also. The processor also measures the number of times n pulses occur in a selectable time window and compares this multiplet distribution to a Poisson distribution as a method of determining the occurrence of fission. The detectors respond to radiation emitted in the fission process induced internally by inherent sources or by external sources such as LINACS, DT generators either pulsed or steady state with alpha detectors, etc. Data can be acquired from prompt emission during the source pulse, prompt emissions immediately after the source pulse, or delayed emissions between source pulses. These types of time coincidence measurements (occurring on the time scale of the fission chain multiplication processes for nuclear weapons grade U and Pu) are useful for determining the presence of these fissile materials and quantifying the amount, and are useful for counter terrorism and nuclear material control and accountability. This paper presents the results for a variety of measurements

  2. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    International Nuclear Information System (INIS)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I.

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (author)

  3. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (autho0008.

  4. SAFIRE - a robotic inspection system for CANDU feeders

    International Nuclear Information System (INIS)

    Buckingham, R.

    2011-01-01

    The condition of primary circuit feeder pipes in CANDU reactors is relevant to the commercial viability and plant life. One known wear mechanism is external fretting between feeder pipes and adjacent services or support structures, particularly within the Upper Feeder Cabinet (UFC). Fretting leads to wall thinning which must not exceed certain agreed limits. Chafe shields have been added to protect the feeder pipes. Regular inspections are required of the chafe shields, feeder pipes and other structures that may cause feeder damage. Historically, the dose received by inspectors conducting this work has been significant. For this reason Ontario Power Generation has invested in a remotely operated robot system to conduct visual inspections within the UFC. This system, called SAFIRE for 'Snake-Arm Feeder Inspection Robot Equipment' has been deployed at Pickering during 2010 and 2011 and has been used to inspect areas that are extremely difficult to inspect with existing manual techniques. The 2011 scope of work included inspection of a total of 660 feeder pipes in three UFC quadrants, in two reactors. The full scope was completed over a one-month period in Autumn 2011 in which SAFIRE was used during 23, twelve hour shifts. This included two periods each of 72 hours of continuous operation using multiple teams of operators. SAFIRE is remote controlled delivery system for multiple cameras to record still images and video. The main system elements include a snake-arm robot mounted on a mobile vehicle. It can be controlled from up to 500m away using a fibre/copper connection. The snake-arm is 2.2m long, 25mm wide and has 18 degrees of freedom. It is designed to snake between the rows of feeder pipes to inspect feeder/hanger interfaces, both above and below the feeder cabinet catwalks. Future upgrades offer the potential to add additional tools to increase functionality. This paper describes the SAFIRE development process from inception to operational experience gained

  5. SAFIRE - a robotic inspection system for CANDU feeders

    Energy Technology Data Exchange (ETDEWEB)

    Buckingham, R. [OC Robotics, Bristol (United Kingdom)

    2011-07-01

    The condition of primary circuit feeder pipes in CANDU reactors is relevant to the commercial viability and plant life. One known wear mechanism is external fretting between feeder pipes and adjacent services or support structures, particularly within the Upper Feeder Cabinet (UFC). Fretting leads to wall thinning which must not exceed certain agreed limits. Chafe shields have been added to protect the feeder pipes. Regular inspections are required of the chafe shields, feeder pipes and other structures that may cause feeder damage. Historically, the dose received by inspectors conducting this work has been significant. For this reason Ontario Power Generation has invested in a remotely operated robot system to conduct visual inspections within the UFC. This system, called SAFIRE for 'Snake-Arm Feeder Inspection Robot Equipment' has been deployed at Pickering during 2010 and 2011 and has been used to inspect areas that are extremely difficult to inspect with existing manual techniques. The 2011 scope of work included inspection of a total of 660 feeder pipes in three UFC quadrants, in two reactors. The full scope was completed over a one-month period in Autumn 2011 in which SAFIRE was used during 23, twelve hour shifts. This included two periods each of 72 hours of continuous operation using multiple teams of operators. SAFIRE is remote controlled delivery system for multiple cameras to record still images and video. The main system elements include a snake-arm robot mounted on a mobile vehicle. It can be controlled from up to 500m away using a fibre/copper connection. The snake-arm is 2.2m long, 25mm wide and has 18 degrees of freedom. It is designed to snake between the rows of feeder pipes to inspect feeder/hanger interfaces, both above and below the feeder cabinet catwalks. Future upgrades offer the potential to add additional tools to increase functionality. This paper describes the SAFIRE development process from inception to operational experience

  6. High-speed railway signal trackside equipment patrol inspection system

    Science.gov (United States)

    Wu, Nan

    2018-03-01

    High-speed railway signal trackside equipment patrol inspection system comprehensively applies TDI (time delay integration), high-speed and highly responsive CMOS architecture, low illumination photosensitive technique, image data compression technique, machine vision technique and so on, installed on high-speed railway inspection train, and achieves the collection, management and analysis of the images of signal trackside equipment appearance while the train is running. The system will automatically filter out the signal trackside equipment images from a large number of the background image, and identify of the equipment changes by comparing the original image data. Combining with ledger data and train location information, the system accurately locate the trackside equipment, conscientiously guiding maintenance.

  7. New design environment for defect detection in web inspection systems

    Science.gov (United States)

    Hajimowlana, S. Hossain; Muscedere, Roberto; Jullien, Graham A.; Roberts, James W.

    1997-09-01

    One of the aims of industrial machine vision is to develop computer and electronic systems destined to replace human vision in the process of quality control of industrial production. In this paper we discuss the development of a new design environment developed for real-time defect detection using reconfigurable FPGA and DSP processor mounted inside a DALSA programmable CCD camera. The FPGA is directly connected to the video data-stream and outputs data to a low bandwidth output bus. The system is targeted for web inspection but has the potential for broader application areas. We describe and show test results of the prototype system board, mounted inside a DALSA camera and discuss some of the algorithms currently simulated and implemented for web inspection applications.

  8. Plane development of lateral surfaces for inspection systems

    Science.gov (United States)

    Francini, F.; Fontani, D.; Jafrancesco, D.; Mercatelli, L.; Sansoni, P.

    2006-08-01

    The problem of developing the lateral surfaces of a 3D object can arise in item inspection using automated imaging systems. In an industrial environment, these control systems typically work at high rate and they have to assure a reliable inspection of the single item. For compactness requirements it is not convenient to utilise three or four CCD cameras to control all the lateral surfaces of an object. Moreover it is impossible to mount optical components near the object if it is placed on a conveyor belt. The paper presents a system that integrates on a single CCD picture the images of both the frontal surface and the lateral surface of an object. It consists of a freeform lens mounted in front of a CCD camera with a commercial lens. The aim is to have a good magnification of the lateral surface, maintaining a low aberration level for exploiting the pictures in an image processing software. The freeform lens, made in plastics, redirects the light coming from the object to the camera lens. The final result is to obtain on the CCD: - the frontal and lateral surface images, with a selected magnification (even with two different values for the two images); - a gap between these two images, so an automatic method to analyse the images can be easily applied. A simple method to design the freeform lens is illustrated. The procedure also allows to obtain the imaging system modifying a current inspection system reducing the cost.

  9. Ultra-low field MRI food inspection system prototype

    Energy Technology Data Exchange (ETDEWEB)

    Kawagoe, Satoshi, E-mail: s133413@edu.tut.ac.jp; Toyota, Hirotomo; Hatta, Junichi; Ariyoshi, Seiichiro; Tanaka, Saburo, E-mail: tanakas@ens.tut.ac.jp

    2016-11-15

    Highlights: • We have developed a ULF-MRI system using HTS-SQUID for food inspection. • We developed a compact magnetically shielded box to attenuate environmental noise. • The 2D-MR image was reconstructed from the grid processing data using 2D-FFT method. • The 2D-MR images of a disk-shaped and a multiple cell water sample were obtained. • The results showed the possibility of applying the ULF-MRI system to food inspection. - Abstract: We develop an ultra-low field (ULF) magnetic resonance imaging (MRI) system using a high-temperature superconducting quantum interference device (HTS-SQUID) for food inspection. A two-dimensional (2D)-MR image is reconstructed from the grid processing raw data using the 2D fast Fourier transform method. In a previous study, we combined an LC resonator with the ULF-MRI system to improve the detection area of the HTS-SQUID. The sensitivity was improved, but since the experiments were performed in a semi-open magnetically shielded room (MSR), external noise was a problem. In this study, we develop a compact magnetically shielded box (CMSB), which has a small open window for transfer of a pre-polarized sample. Experiments were performed in the CMSB and 2D-MR images were compared with images taken in the semi-open MSR. A clear image of a disk-shaped water sample is obtained, with an outer dimension closer to that of the real sample than in the image taken in the semi-open MSR. Furthermore, the 2D-MR image of a multiple cell water sample is clearly reconstructed. These results show the applicability of the ULF-MRI system in food inspection.

  10. Inspection of secondary cooling system piping of JMTR

    International Nuclear Information System (INIS)

    Hanawa, Yoshio; Izumo, Hironobu; Fukasaku, Akitomi; Nagao, Yoshiharu; Kawamura, Hiroshi

    2008-06-01

    Piping condition was inspected form the view point of long term utilization before the renewal work of the secondary cooling system in the JMTR on FY 2008. As the result, it was confirmed that cracks, swellings and exfoliations in inner lining of the piping could be observed, and corrosion, which was reached by piping ingot, or decrease of piping thickness could hardly be observed. It was therefore confirmed that the strength or the functionality of the piping had been maintained by usual operation and maintenance. Repair of inner lining of the piping during the refurbishment of the JMTR is necessary to long term utilization of the secondary cooling system after restart of the JMTR from the view point of preventive maintenance. In addition, a periodic inspection of inner lining condition is necessary after repair of the piping. (author)

  11. THE INSPECTION LIKE QUALITY FACTOR IN THE EDUCATIONAL SYSTEM

    Directory of Open Access Journals (Sweden)

    Joaquín Oliver Pozo

    2016-07-01

    Full Text Available The Inspection, along with other educational sectors, shapes from complementarity, coordination and communication between them, the architecture of the educational system. Each has its specificity and its own space in Education. The aim of this study is simply identify and define the location of the inspection into the education system, between educational administration and schools, and the "why" (their mission, and consistent with it, "which makes" (its functions and assignations. Mission and functions that take place in schools, at the sight of the Educational Administration and the society, through the Inspectorate as organization. Of the principles underlying this organization and of the communication, training, and technical and professional exchange that drives through their organizational structures, will depend its leadership in Education and to be seen as a quality factor.

  12. Development of the EURITRACK tagged neutron inspection system

    International Nuclear Information System (INIS)

    Perot, B.; Carasco, C.; Bernard, S.

    2007-01-01

    The EURopean Illicit TRAfficing Countermeasures Kit (EURITRACK) project is part of the 6th European Union Framework Program. It aims at developing a Tagged Neutron Inspection System (TNIS) to detect illicit materials, such as explosives and narcotics, in cargo containers. Fast neutron induced reactions produce specific gamma-rays used to determine the chemical composition of the inspected material. The associated particle technique is employed to precisely locate the interaction points of the neutrons. A new deuterium-tritium neutron generator has been developed, including a pixelized alpha particle detector. The TNIS also comprises high-efficiency fast neutron and gamma-ray detectors, a dedicated front-end electronics and an integrated software to entirely drive the system and automatically process the data. Most components have been integrated during last months at Institute Ruder Boskovic, in Zagreb, Croatia. An overview of the TNIS and of its preliminary performances is presented

  13. Towards an automated checked baggage inspection system augmented with robots

    Science.gov (United States)

    DeDonato, Matthew P.; Dimitrov, Velin; Padır, Taskin

    2014-05-01

    We present a novel system for enhancing the efficiency and accuracy of checked baggage screening process at airports. The system requirements address the identification and retrieval of objects of interest that are prohibited in a checked luggage. The automated testbed is comprised of a Baxter research robot designed by Rethink Robotics for luggage and object manipulation, and a down-looking overhead RGB-D sensor for inspection and detection. We discuss an overview of current system implementations, areas of opportunity for improvements, robot system integration challenges, details of the proposed software architecture and experimental results from a case study for identifying various kinds of lighters in checked bags.

  14. Laboratory evaluation of two x-ray baggage inspection systems

    International Nuclear Information System (INIS)

    Schellenbaum, R.L.

    1979-06-01

    The AS and E Micro-Dose X-ray Baggage Inspection System was designed for high-volume, detailed examination of packages at ultralow x-ray exposure levels. This system is used in airline terminals for the detection of weapons, bombs, and other contraband. It is also employed by security personnel in other facilities to search packages for contraband carried in and out of secured areas. The Micro-Dose system has a unique design concept which includes an Automatic Threat Alert System (ATA) and a zoom display presentation feature

  15. Automated phased array ultrasonic inspection system for rail wheel sets

    International Nuclear Information System (INIS)

    Grosser, Paul; Weiland, M.G.

    2013-01-01

    This paper covers the design, system automation, calibration and validation of an automated ultrasonic system for the inspection of new and in service wheel set assemblies from diesel-electric locomotives and gondola cars. This system uses Phased Array (PA) transducers for flaw detection and Electro-Magnetic Acoustic Transducers (EMAT) for the measurement of residual stress. The system collects, analyses, evaluates and categorizes the wheel sets automatically. This data is archived for future comparison and trending. It is also available for export to a portal lathe for increased efficiency and accuracy of machining, therefore allowing prolonged wheel life.

  16. LHC train control system for autonomous inspections and measurements

    OpenAIRE

    Di Castro, Mario; Baiguera Tambutti, Maria Laura; Gilardoni, Simone; Losito, Roberto; Lunghi, Giacomo; Masi, Alessandro

    2018-01-01

    Intelligent robotic systems are becoming essential for inspection and measurements in harsh environments, such as the European Organization for Nuclear Research (CERN) accelerators complex. Aiming at increasing safety and machine availability, robots can help to perform repetitive or dangerous tasks, reducing the risk for the personnel as the exposure to radiation. The Large Hadron Collider (LHC) tunnel at CERN has been equipped with fail-safe trains on monorail able to perform autonomously d...

  17. International cooperative information systems

    International Nuclear Information System (INIS)

    1980-01-01

    Developing countries need mechanisms by which the information they generate themselves and development information from the rest of the world can be retrieved. The international cooperative information system is such a mechanism. Delegates to the Seminar on International Cooperative Information Systems were informed about various existing systems (INIS, AGRIS, INFOTERRA, TCDC/INRES, POPIN, DEVSIS, and INPADROC), some specialized information systems and services (CDS/ISIS and the Cassava Information Centre), and computer programs for information processing (INIS/AGRIS, CDS/ISIS, and MINISIS). The participants suggested some changes that should be made on both the national and the international levels to ensure that these systems meet the needs of developing countries more effectively. (LL)

  18. 14 CFR 21.125 - Production inspection system: Materials Review Board.

    Science.gov (United States)

    2010-01-01

    ... § 21.125 Production inspection system: Materials Review Board. Link to an amendment published at 74 FR... Materials Review Board action for at least two years. (b) The production inspection system required in § 21... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Production inspection system: Materials...

  19. Applications Of A Low Cost System For Industrial Automatic Inspection

    Science.gov (United States)

    Krey, C.; Ayache, A.; Bruel, A.

    1987-05-01

    In industrial environment, some repetitive tasks wich do not need a high degree of understanding, can be solved automatically owing to Vision. Among the systems available on the market, most of them are rather expensive with various capabilities. The described system is a modular system, built with some standard circuit boards. One of the advantages of this system is that its architecture can be redefined for each application, by assembling judiciously the standard modules. The vision system has been used successfully to sort fruits according to their colour and diameter. The system can sort 8 fruits per second on each sorting line and manage simultaneously up to 16 lines. An application of sheep skin cutting has been implemented too. After chemical and mechanical treatments, the skins present many defaults all around their contour, that must be cut off. A movable camera follows and inspects the contour ; the vision system determines where the cutting device must cut the skin. A third application has been implemented ; it concerns automatic recording and reproduction of logotypes. A moving camera driven by the system picks up the points, of the logotype contours. Before reproduction, programs can modify the logotypes shape, change the scale, and so on. For every application, the system uses the world smallest CCD camera developped in the laboratory. The small dimensions of the vision system and its low cost are major advantages for a wide use in industrial automatic inspection.

  20. Development of inspection and evaluation guidelines for light water reactor internals

    International Nuclear Information System (INIS)

    Aoki, T.; Yamashita, H.; Sakai, K.

    2002-01-01

    Full text: In Japan, before a nuclear power plant reaches its 30 years of operation, the Japanese utilities carry out a 'study on plant life management'. Reflecting the results of that study into the maintenance, the utilities make efforts to maintain and improve the safety and reliability of their nuclear power plants. In this study, all safety related components are evaluated from the viewpoint of aging degradation, assuming a long-term operation. If a crack should be found at components such as reactor internals, which is deemed important for safety and are difficult to repair or replace may provide a serious impact on the plant operation and management. Reactor internals, for instance, made of austenitic stainless steel and nickel base alloy, are not completely free from aging degradation including stress corrosion cracking (SCC). Therefore, it is concluded in the study on plant life management that they are required continuous planned inspections to confirm their integrity while continuing plant operation. If an aging degradation such as SCC should be found at the reactor internals, a great amount of labor and time may be required for root cause investigation and analysis and subsequent repairs because it is very difficult to reach to the degraded portion due to structural, dimensional and environmental restrictions. Therefore, such situations may provide serious impact on plant operation and management. As to the reactor internals and other components with similar characteristics, it is strongly recommended that contingency plan should be prepared in advance. Thus, considering the significance of aging degradation, it is necessary to develop some standard rules for the inspection and evaluation of reactor internals. Such rules should specify when, where and how to inspect. They should also specify the evaluation method in case such degradation as a crack is found, and the repair method and extent if repairs are required. These standard rules must be

  1. 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.)

  2. 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

  3. Influence Of Inspection Intervals On Mechanical System Reliability

    International Nuclear Information System (INIS)

    Zilberman, B.

    1998-01-01

    In this paper a methodology of reliability analysis of mechanical systems with latent failures is described. Reliability analysis of such systems must include appropriate usage of check intervals for latent failure detection. The methodology suggests, that based on system logic the analyst decides at the beginning if a system can fail actively or latently and propagates this approach through all system levels. All inspections are assumed to be perfect (all failures are detected and repaired and no new failures are introduced as a result of the maintenance). Additional assumptions are that mission time is much smaller, than check intervals and all components have constant failure rates. Analytical expressions for reliability calculates are provided, based on fault tree and Markov modeling techniques (for two and three redundant systems with inspection intervals). The proposed methodology yields more accurate results than are obtained by not using check intervals or using half check interval times. The conventional analysis assuming that at the beginning of each mission system is as new, give an optimistic prediction of system reliability. Some examples of reliability calculations of mechanical systems with latent failures and establishing optimum check intervals are provided

  4. Vision systems for the inspection of resistance welding joints

    Science.gov (United States)

    Hildebrand, Lars; Fathi, Madjid

    2000-06-01

    Many automated quality inspection systems make use of brightness and contrast features of the objects being inspected. This reduces the complexity of the problem solving methods, as well as the demand for computational capacity. Nevertheless a lot of significant information is located in color features of the objects. This paper describes a method, that allows the evaluation of color information in a very compact and efficient way. The described method uses a combination of multi-valued logic and a special color model. We use fuzzy logic as multi-valued logic, and the HSI color model, but any multi-valued logic, that allows rule-based reasoning can be used. The HSI color model can also be exchanged with other color models, if special demands require this.

  5. Advanced Visualization Software System for Nuclear Power Plant Inspection

    International Nuclear Information System (INIS)

    Kukic, I.; Jambresic, D.; Reskovic, S.

    2006-01-01

    Visualization techniques have been widely used in industrial environment for enhancing process control. Traditional techniques of visualization are based on control panels with switches and lights, and 2D graphic representations of processes. However, modern visualization systems enable significant new opportunities in creating 3D virtual environments. These opportunities arise from the availability of high end graphics capabilities in low cost personal computers. In this paper we describe implementation of process visualization software, developed by INETEC. This software is used to visualize testing equipment, components being tested and the overall power plant inspection process. It improves security of the process due to its real-time visualization and collision detection capabilities, and therefore greatly enhances the inspection process. (author)

  6. Flexible mobile robot system for smart optical pipe inspection

    Science.gov (United States)

    Kampfer, Wolfram; Bartzke, Ralf; Ziehl, Wolfgang

    1998-03-01

    Damages of pipes can be inspected and graded by TV technology available on the market. Remotely controlled vehicles carry a TV-camera through pipes. Thus, depending on the experience and the capability of the operator, diagnosis failures can not be avoided. The classification of damages requires the knowledge of the exact geometrical dimensions of the damages such as width and depth of cracks, fractures and defect connections. Within the framework of a joint R&D project a sensor based pipe inspection system named RODIAS has been developed with two partners from industry and research institute. It consists of a remotely controlled mobile robot which carries intelligent sensors for on-line sewerage inspection purpose. The sensor is based on a 3D-optical sensor and a laser distance sensor. The laser distance sensor is integrated in the optical system of the camera and can measure the distance between camera and object. The angle of view can be determined from the position of the pan and tilt unit. With coordinate transformations it is possible to calculate the spatial coordinates for every point of the video image. So the geometry of an object can be described exactly. The company Optimess has developed TriScan32, a special software for pipe condition classification. The user can start complex measurements of profiles, pipe displacements or crack widths simply by pressing a push-button. The measuring results are stored together with other data like verbal damage descriptions and digitized images in a data base.

  7. Design and implementation for integrated UAV multi-spectral inspection system

    Science.gov (United States)

    Zhu, X.; Li, X.; Yan, F.

    2018-04-01

    In order to improve the working efficiency of the transmission line inspection and reduce the labour intensity of the inspectors, this paper presents an Unmanned Aerial Vehicle (UAV) inspection system architecture for the transmission line inspection. In this document, the light-duty design for different inspection equipment and processing terminals is completed. It presents the reference design for the information-processing terminal, supporting the inspection and interactive equipment accessing, and obtains all performance indicators of the inspection information processing through the tests. Practical application shows that the UAV inspection system supports access and management of different types of mainstream fault detection equipment, and can implement the independent diagnosis of the detected information to generate inspection reports in line with industry norms, which can meet the fast, timely, and efficient requirements for the power line inspection work.

  8. Robotized system for in-pipe inspection using pressure tolerant electronics technique

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Ramon R.; Hsu, Liu; Peixoto, Alessandro J.; Gomes, Luiz P.C.S. [Coordenacao dos Programas de Pos-graduacao de Engenharia (UFRJ/COPPE), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica. Grupo de Simulacao e Controle em Automacao e Robotica (GSCAR)]. E-mail: ramon, liu, jacoud, lpgomes@coep.ufrj.br; Reis, Ney R.S. dos [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil). Centro de Pesquisas. Lab. de Robotica]. E-mail: salvireis@cenpes.petrobras.com.br

    2003-07-01

    This paper reports the development and experimental evaluation of a robotized system devised to perform two kinds of measurements inside a pipeline: the thickness of the internal wall painting layer and the internal radius. The thickness measurement allows the inspection of the painting layer quality and by measuring several radii it is possible to estimate the pipeline transversal section shape. The proposed scheme is shown to yield very satisfactory results on an actual 14'' (inches) pipeline in a real site. (author)

  9. Computer control in nondestructive testing illustrated by an automatic ultrasonic tube inspection system

    International Nuclear Information System (INIS)

    Gundtoft, H.E.; Nielsen, N.

    1976-06-01

    In Risoe's automatic tube inspection system, data (more than half a million per tube) from ultrasonic dimension measurements and defect inspections are fed into a computer that simultaneously calculates and evaluates the results. (author)

  10. Evaluation of robotic inspection systems at nuclear power plants

    International Nuclear Information System (INIS)

    White, J.R.; Eversole, R.E.; Farnstrom, K.A.; Harvey, H.W.; Martin, H.L.

    1984-03-01

    This report presents and demonstrates a cost-effective approach for robotics application (CARA) to surveillance and inspection work in existing nuclear power plants. The CARA was developed by the Remote Technology Corporation to systematically determine the specific surveillance/inspection tasks, worker hazards, and access or equipment placement restraints in each of the many individual rooms or areas at a power plant. Guidelines for designing inspection robotics are included and are based upon the modular arrangement of commercially-available sensors and other components. Techniques for maximizing the cost effectiveness of robotics are emphasized in the report including: selection of low-cost robotic components, minimal installation work in plant areas, portable systems for common use in different areas, and standardized robotic modules. Factors considered as benefits are reduced radiation exposure, lower man-hours, shorter power outage, less waste material, and improved worker safety concerns. A partial demonstration of the CARA methodology to the Sequoyah (PWR) and Browns Ferry (BWR) Plants is provided in the report along with specific examples of robotic installations in high potential areas

  11. Automated visual inspection system based on HAVNET architecture

    Science.gov (United States)

    Burkett, K.; Ozbayoglu, Murat A.; Dagli, Cihan H.

    1994-10-01

    In this study, the HAusdorff-Voronoi NETwork (HAVNET) developed at the UMR Smart Engineering Systems Lab is tested in the recognition of mounted circuit components commonly used in printed circuit board assembly systems. The automated visual inspection system used consists of a CCD camera, a neural network based image processing software and a data acquisition card connected to a PC. The experiments are run in the Smart Engineering Systems Lab in the Engineering Management Dept. of the University of Missouri-Rolla. The performance analysis shows that the vision system is capable of recognizing different components under uncontrolled lighting conditions without being effected by rotation or scale differences. The results obtained are promising and the system can be used in real manufacturing environments. Currently the system is being customized for a specific manufacturing application.

  12. Relocatable cargo x-ray inspection systems utilizing compact linacs

    International Nuclear Information System (INIS)

    Sapp, W. Wade; Adams, William L.; Callerame, Joseph; Grodzins, Lee; Rothschild, Peter J.; Schueller, Richard; Mishin, Andrey V.; Smith, Gerald J.

    2001-01-01

    Magnetron-powered, X-band linacs with 3-4 MeV capability are compact enough to be readily utilized in relocatable high energy cargo inspection systems. Just such a system is currently under development at AS and E trade mark sign using the commercially available ISOSearch trade mark sign cargo inspection system as the base platform. The architecture permits the retention of backscatter imaging, which has proven to be an extremely valuable complement to the more usual transmission images. The linac and its associated segmented detector will provide an additional view with superior penetration and spatial resolution. The complete system, which is housed in two standard 40 ' ISO containers, is briefly described with emphasis on the installation and operating characteristics of the portable linac. The average rf power delivered by the magnetron to the accelerator section can be varied up to the maximum of about 1 kW. The projected system performance, including radiation dose to the environment, will be discussed and compared with other high energy systems

  13. To develop a flying fish egg inspection system by a digital imaging base system

    Science.gov (United States)

    Chen, Chun-Jen; Jywe, Wenyuh; Hsieh, Tung-Hsien; Chen, Chien Hung

    2015-07-01

    This paper develops an automatic optical inspection system for flying fish egg quality inspection. The automatic optical inspection system consists of a 2-axes stage, a digital camera, a lens, a LED light source, a vacuum generator, a tube and a tray. This system can automatically find the particle on the flying egg tray and used stage to driver the tube onto the particle. Then use straw and vacuum generator to pick up the particle. The system pick rate is about 30 particles per minute.

  14. Development of a remote tank inspection robotic system

    International Nuclear Information System (INIS)

    Knape, B.P.; Bares, L.C.

    1990-01-01

    RedZone Robotics is currently developing a remote tank inspection (RTI) robotic system for Westinghouse Idaho Nuclear Company (WINCO). WINCO intends to use the RTI robotic system at the Idaho Chemical Processing Plant, a facility that contains a tank farm of several 1,135,500-ell (300,000-gal), 15.2-m (50-ft)-diam, high-level liquid waste storage tanks. The primary purpose of the RTI robotic system is to inspect the interior of these tanks for corrosion that may have been caused by the combined effects of radiation, high temperature, and caustic by the combined effects of radiation, high temperature, and caustic chemicals present inside the tanks. The RTI robotic system features a vertical deployment unit, a robotic arm, and a remote control console and computer [located up to 30.5 m (100 ft) away from the tank site]. All actuators are high torque, electric dc brush motors that are servocontrolled with absolute position feedback. The control system uses RedZone's standardized intelligent controller for enhanced telerobotics, which provides a high speed, multitasking environment on a VME bus. Currently, the robot is controlled in a manual, job-button, control mode; however, control capability is available to develop preprogrammed, automated modes of operation

  15. A development of an automated ultrasonic TOFD inspection system using an welding line tracing robot

    International Nuclear Information System (INIS)

    Cho, Hyun; Song, Sung Jin; Lee, Kang Won; Kim, Young Jin; Woo, Jong Sik

    2006-01-01

    Large scaled ships, manufactured inside of the country, should be passed welding inspection and painting film inspection. Normally, these kind of inspections are conducted by human inspectors manually, although it cause industrial disasters such as falling accidents and diving accidents frequently. In addition, Ship makers are not to give a full trust to shipowners because manual inspections cannot be conducted all over the welding parts. So, in this study we developed an automated ultrasonic TOFD inspection system using an welding line tracing robot. This system, controlled by an inspector at a remote field, can inspect welding parts of ship outer panel both under water and in air. In this paper we present the developed robot and ultrasonic TOFD inspection system and the inspection result.

  16. A development of an automated ultrasonic TOFD inspection system using an welding line tracing robot

    International Nuclear Information System (INIS)

    Cho, Hyun; Song, Sung Jin; Lee, Kang Won; Kim, Young Jin; Woo, Jong Sik

    2006-01-01

    Large scaled ships, manufactured inside of the country, should be passed welding inspection and painting film inspection. Normally, these kind of inspections are conducted by human inspectors manually, although it cause industrial disasters such as falling accidents and diving accidents frequently. In addition, Ship makers are not to give a full trust to ship owners because manual inspections cannot be conducted all over the welding parts. So, in this study we developed an automated ultrasonic TOFD inspection system using an welding line tracing robot. This system, controlled by an inspector at a remote field, can inspect welding parts of ship outer panel both under water and in air. In this paper we present the developed robot and ultrasonic TOFD inspection system and the inspection result.

  17. Internal control system

    OpenAIRE

    Pavésková, Ivana

    2014-01-01

    Dissertation focuse on the internal control system in the enterprises, aims to map the control system by focusing on the purchasing department. I focused on the purchasing process, because with an increasing trends of outsourcing services and the increasing interconnectedness of enterprises increases the risk of fraud currently in the purchasing process. To the research was selected the sample of companies from the banking and non-banking environment, to which were sent a questionnaire focusi...

  18. Development on multifunctional phased-array fault inspection technology. Aiming at integrity on internals in nuclear power plant reactors

    International Nuclear Information System (INIS)

    Komura, Ichiro; Hirasawa, Taiji; Nagai, Satoshi; Naruse, Katsuhiko

    2002-01-01

    On nuclear power plants sharing an important role in Japanese energy policy, their higher safety and reliability than the other plants are required, and their non-destructive inspection occupies important position for information means to judge their integrity. And, for a part of responses to recent rationalization of the plant operation and increase of aged plants, requirements and positioning onto the non-destructive inspection technology also change. As a result, not only concept on allowable fault sizes is adopted, but also inspection on reactor internals without conventional regulation is obliged to require for size evaluation (sizing) with higher precision to use for secure detection and integrity evaluation of the faults than sizes determined for every internals. For requirement with such higher levels for fault detection and sizing, and for requirement for effective inspection, phased-array supersonic wave fault inspection method is one of the methods with high potential power. Here were introduced on principles and characteristics of the phased-array supersonic wave fault inspection method, and on various fault inspection methods and functions mainly developed for reactor internals inspection. (G.K.)

  19. Linac based photofission inspection system employing novel detection concepts

    Energy Technology Data Exchange (ETDEWEB)

    Stevenson, John, E-mail: jstevenson@rapiscansystems.com [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States); Gozani, Tsahi, E-mail: tgozani@rapiscansystems.com [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States); Elsalim, Mashal; Condron, Cathie; Brown, Craig [Rapiscan Laboratories, Inc., 520 Almanor Avenue, Sunnyvale, CA 94085 (United States)

    2011-10-01

    Rapiscan Systems is developing a LINAC based cargo inspection system for detection of special nuclear material (SNM) in cargo containers. The system, called Photofission Based Alarm Resolution (PBAR) is being developed under a DHD/DNDO Advanced Technology Demonstration (ATD) program. The PBAR system is based on the Rapiscan Eagle P9000 X-ray system, which is a portal system with a commercial 9 MeV LINAC X-ray source. For the purposes of the DNDO ATD program, a conveyor system was installed in the portal to allow scanning and precise positioning of 20 ft ISO cargo containers. The system uses a two step inspection process. In the first step, the basic scan, the container is quickly and completely inspected using two independent radiography arrays: the conventional primary array with high spatial resolution and a lower resolution spectroscopic array employing the novel Z-Spec method. The primary array uses cadmium tungstate (CdWO{sub 4}) detectors with conventional current mode readouts using photodiodes. The Z-Spec array uses small plastic scintillators capable of performing very fast (up to 10{sup 8} cps) gamma-ray spectroscopy. The two radiography arrays are used to locate high-Z objects in the image such as lead, tungsten, uranium, which could be potential shielding materials as well as SNM itself. In the current system, the Z-Spec works by measuring the energy spectrum of transmitted X-rays. For high-Z materials the higher end of the energy spectrum is more attenuated than for low-Z materials and thus has a lower mean energy and a narrower width than low- and medium-Z materials. The second step in the inspection process is the direct scan or alarm clearing scan. In this step, areas of the container image, which were identified as high Z, are re-inspected. This is done by precisely repositioning the container to the location of the high-Z object and performing a stationary irradiation of the area with X-ray beam. Since there are a large number of photons in the 9

  20. Linac based photofission inspection system employing novel detection concepts

    International Nuclear Information System (INIS)

    Stevenson, John; Gozani, Tsahi; Elsalim, Mashal; Condron, Cathie; Brown, Craig

    2011-01-01

    Rapiscan Systems is developing a LINAC based cargo inspection system for detection of special nuclear material (SNM) in cargo containers. The system, called Photofission Based Alarm Resolution (PBAR) is being developed under a DHD/DNDO Advanced Technology Demonstration (ATD) program. The PBAR system is based on the Rapiscan Eagle P9000 X-ray system, which is a portal system with a commercial 9 MeV LINAC X-ray source. For the purposes of the DNDO ATD program, a conveyor system was installed in the portal to allow scanning and precise positioning of 20 ft ISO cargo containers. The system uses a two step inspection process. In the first step, the basic scan, the container is quickly and completely inspected using two independent radiography arrays: the conventional primary array with high spatial resolution and a lower resolution spectroscopic array employing the novel Z-Spec method. The primary array uses cadmium tungstate (CdWO 4 ) detectors with conventional current mode readouts using photodiodes. The Z-Spec array uses small plastic scintillators capable of performing very fast (up to 10 8 cps) gamma-ray spectroscopy. The two radiography arrays are used to locate high-Z objects in the image such as lead, tungsten, uranium, which could be potential shielding materials as well as SNM itself. In the current system, the Z-Spec works by measuring the energy spectrum of transmitted X-rays. For high-Z materials the higher end of the energy spectrum is more attenuated than for low-Z materials and thus has a lower mean energy and a narrower width than low- and medium-Z materials. The second step in the inspection process is the direct scan or alarm clearing scan. In this step, areas of the container image, which were identified as high Z, are re-inspected. This is done by precisely repositioning the container to the location of the high-Z object and performing a stationary irradiation of the area with X-ray beam. Since there are a large number of photons in the 9 MV

  1. Inspection, evaluation and maintenance guidelines for reactor vessel internals in JAPAN

    International Nuclear Information System (INIS)

    Sakashita, Akihiro; Goto, Tomoya; Hirano, Shinro; Dozaki, Koji

    2010-01-01

    Inspection and Evaluation Guidelines for reactor internals has been taken into the Rules on Fitness-for–Service for Nuclear Power Plants of The Japan Society of Mechanical Engineers. It is a base of the maintenance plan of each Nuclear Power Plant. A plant maintenance methodology will have more importance to maintain the plant safety and stable plant operation. This paper introduces the systematization of the maintenance such as repair, replacement, preventive maintenance in these guidelines. Maintenance methodologies are classified follows. Repair: methodology to reinforce degraded parts by some methods or prevent progress of degradation of without replacement of the existing structure when the degradation of structure is actualized. Replacement: methodology to replace the existing structure with new one when the degradation of structure is actualized. Preventive maintenance : methodology to mitigate the damaged condition. When the maintenance methodologies are implemented in the actual plant, we have to consider the feedback of the inspection program and plant life management. (author)

  2. Noncontact inspection laser system for characterization of piezoelectric samples

    International Nuclear Information System (INIS)

    Jimenez, F.J.; Frutos, J. de

    2004-01-01

    In this work measurements on a piezoelectric sample in dynamic behavior were taken, in particular, around the frequencies of resonance for the sample where the nonlineal effects are accentuated. Dimension changes in the sample need to be studied as that will allow a more reliable characterization of the piezoelectric samples. The goal of this research is to develop an inspection system able to obtain measurements, using a noncontact laser displacement transducer, also able to visualize, in three-dimensional graphic environment, the displacement that takes place in a piezoelectric sample surface. In resonant mode, the vibration mode of the sample is visualized

  3. High performance coated board inspection system based on commercial components

    CERN Document Server

    Barjaktarovic, M; Radunovic, J

    2007-01-01

    This paper presents a vision system for defect (fault) detection on a coated board developed using three industrial firewire cameras and a PC. Application for image processing and system control was realized with the LabView software package. Software for defect detection is based on a variation of the image segmentation algorithm. Standard steps in image segmentation are modified to match the characteristics of defects. Software optimization was accomplished using SIMD (Single Instruction Multiple Data) technology available in the Intel Pentium 4 processors that provided real time inspection capability. System provides benefits such as: improvement in production process, higher quality of delivered coated board and reduction of waste. This was proven during successful exploitation of the system for more than a year.

  4. ARCHER-Advanced System for RPVH Inspection and Repair

    International Nuclear Information System (INIS)

    Tomasic, Tomislav; Vukovic, Igor; Bakic, Ante

    2014-01-01

    The reactor pressure vessel head (RPVH) is an integral part of the reactor coolant pressure boundary. Its integrity is important for the safe and reliable operation of the nuclear power plant (NPP). After detection of the leakage and cracks in French NPP, followed by another that occurred in NPP in USA, methods and frequency of inspection were defined, and are strictly regulated by the US NRC Order EA-03-009 (substituted lately by ASME Code Case N-791-1) since 2003. Usual scope of inspection from inner side of RPVH comprises of visual inspection of the surface, ultrasonic testing (UT) and eddy current testing (ET) of the penetration nozzle and ET of the J-groove weld and nozzle outside surface below the weld. ARCHER, new INETEC's manipulator, is designed to provide full scope inspection of the RPVH, by use of various test modules and by performing the surface repair action on J-groove weld. It is adjustable to work with different types of penetration nozzles and thermal sleeves on both VVER and PWR type of NPP. Due to complex geometry each module is specially designed for particular type of examination. Modules are exchanged through the docking system without need for personnel to enter under the head region, thus reducing the personnel's exposure to the ionizing radiation. The end effectors are used to determine the surface flaws or cracks on inner diameter surface of penetration nozzle gap. It guides a slim sword-like probe which carries a pair of TOFD transducers for detection and sizing of circumferential and axial cracks, an eddy current cross-wounded coil, and a zero-degree UT probe through a gap between the penetration nozzle and thermal sleeve. In case of a non-sleeved penetration nozzle, an open housing module is used. J-groove module is designed to fit geometry of the J-groove weld of penetration nozzle, vent pipe and funnel guide. The whole weld area (2' mm on shell side and 1/2' on nozzle side) is covered by two specially designed

  5. A Reference Model for Software and System Inspections. White Paper

    Science.gov (United States)

    He, Lulu; Shull, Forrest

    2009-01-01

    Software Quality Assurance (SQA) is an important component of the software development process. SQA processes provide assurance that the software products and processes in the project life cycle conform to their specified requirements by planning, enacting, and performing a set of activities to provide adequate confidence that quality is being built into the software. Typical techniques include: (1) Testing (2) Simulation (3) Model checking (4) Symbolic execution (5) Management reviews (6) Technical reviews (7) Inspections (8) Walk-throughs (9) Audits (10) Analysis (complexity analysis, control flow analysis, algorithmic analysis) (11) Formal method Our work over the last few years has resulted in substantial knowledge about SQA techniques, especially the areas of technical reviews and inspections. But can we apply the same QA techniques to the system development process? If yes, what kind of tailoring do we need before applying them in the system engineering context? If not, what types of QA techniques are actually used at system level? And, is there any room for improvement.) After a brief examination of the system engineering literature (especially focused on NASA and DoD guidance) we found that: (1) System and software development process interact with each other at different phases through development life cycle (2) Reviews are emphasized in both system and software development. (Figl.3). For some reviews (e.g. SRR, PDR, CDR), there are both system versions and software versions. (3) Analysis techniques are emphasized (e.g. Fault Tree Analysis, Preliminary Hazard Analysis) and some details are given about how to apply them. (4) Reviews are expected to use the outputs of the analysis techniques. In other words, these particular analyses are usually conducted in preparation for (before) reviews. The goal of our work is to explore the interaction between the Quality Assurance (QA) techniques at the system level and the software level.

  6. Inspection and maintenance of HVAC systems : what you need to know; L'inspection et l'entretien des systemes de CVCA : ce qu'il faut savoir

    Energy Technology Data Exchange (ETDEWEB)

    Tapp, D. [Groupe Gesfor Poirier, Pinchin Inc., Montreal, PQ (Canada)

    2010-01-01

    This article described an inspection and maintenance program (IMP) that ensures the cleanliness of building's heating, ventilating and air conditioning (HVAC) system. Air quality can be compromised over time as dust accumulates in filters and on internal surfaces of an HVAC. Since mould spores and bacteria are significant components of dust, an excessive accumulation of dust in an HVAC system can lead to microbiological growth issues, particularly in humid conditions. Damaged dampers, missing screens and clogged or inefficient drains can generate indoor air quality issues. As such, preventive inspection of ventilation systems can identify deficiencies as well as future problems. This article also highlighted the integrated services provided by the Gesfor Poirier, Pinchin Group regarding industrial hygiene, health and safety inspection and remediation of HVAC systems and management of asbestos and other hazardous materials in buildings. 4 figs.

  7. Evaluation of computer-based ultrasonic inservice inspection systems

    International Nuclear Information System (INIS)

    Harris, R.V. Jr.; Angel, L.J.; Doctor, S.R.; Park, W.R.; Schuster, G.J.; Taylor, T.T.

    1994-03-01

    This report presents the principles, practices, terminology, and technology of computer-based ultrasonic testing for inservice inspection (UT/ISI) of nuclear power plants, with extensive use of drawings, diagrams, and LTT images. The presentation is technical but assumes limited specific knowledge of ultrasonics or computers. The report is divided into 9 sections covering conventional LTT, computer-based LTT, and evaluation methodology. Conventional LTT topics include coordinate axes, scanning, instrument operation, RF and video signals, and A-, B-, and C-scans. Computer-based topics include sampling, digitization, signal analysis, image presentation, SAFI, ultrasonic holography, transducer arrays, and data interpretation. An evaluation methodology for computer-based LTT/ISI systems is presented, including questions, detailed procedures, and test block designs. Brief evaluations of several computer-based LTT/ISI systems are given; supplementary volumes will provide detailed evaluations of selected systems

  8. Trajectory-tracking control of underwater inspection robot for nuclear reactor internals using Time Delay Control

    International Nuclear Information System (INIS)

    Park, Joon-Young; Cho, Byung-Hak; Lee, Jae-Kyung

    2009-01-01

    This paper addresses the trajectory control problem of an underwater inspection robot for nuclear reactor internals. From the viewpoint of control engineering, the trajectory control of the underwater robot is a difficult task due to its nonlinear dynamics, which includes various hydraulic forces such as buoyancy and hydrodynamic damping, the difference between the centres of gravity and buoyancy, and disturbances from a tether cable. To solve such problems, we applied Time Delay Control to the underwater robot. This control law has a very simple structure not requiring nonlinear plant dynamics, and was proven to be highly robust against nonlinearities, uncertainties and disturbances. We confirmed its effectiveness through experiments.

  9. The development of in-cell remote inspection system in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishibashi, Yuzo

    1985-01-01

    In the Tokai fuel reprocessing plant, the containment is triple, i.e. the vessel containing radioactive material, then the concrete cell structure and finally the housing building. The fuel reprocessing plant is now proceeding with the development of an in-cell remote inspection system. The inspection system is for inspection of the cell itself and the equipment etc. in the cell, concerning the integrity. Described are the following: the course taken and problems in development of the remote inspection system; development of the floor rambling type remote inspection equipment and the multiple armed type, both for inspection of in-cell ''drip trays''; in-cell equipment inspection devices in specifications etc.; problems in its future development. (Mori, K.)

  10. Advanced algorithms for radiographic material discrimination and inspection system design

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, Andrew J. [Pacific Northwest National Laboratory, Richland, WA 99354 (United States); McDonald, Benjamin S., E-mail: benjamin.mcdonald@pnnl.gov [Pacific Northwest National Laboratory, Richland, WA 99354 (United States); Deinert, Mark R., E-mail: mdeinert@mines.edu [Colorado School of Mines, Golden, CO 80401 (United States)

    2016-10-15

    X-ray and neutron radiography are powerful tools for non-invasively inspecting the interior of objects. However, current methods are limited in their ability to differentiate materials when multiple materials are present, especially within large and complex objects. Past work has demonstrated that the spectral shift that X-ray beams undergo in traversing an object can be used to detect and quantify nuclear materials. The technique uses a spectrally sensitive detector and an inverse algorithm that varies the composition of the object until the X-ray spectrum predicted by X-ray transport matches the one measured. Here we show that this approach can be adapted to multi-mode radiography, with energy integrating detectors, and that the Cramér–Rao lower bound can be used to choose an optimal set of inspection modes a priori. We consider multi-endpoint X-ray radiography alone, or in combination with neutron radiography using deuterium–deuterium (DD) or deuterium–tritium (DT) sources. We show that for an optimal mode choice, the algorithm can improve discrimination between high-Z materials, specifically between tungsten and plutonium, and estimate plutonium mass within a simulated nuclear material storage system to within 1%.

  11. Conceptual design of EAST flexible in-vessel inspection system

    International Nuclear Information System (INIS)

    Peng, X.B.; Song, Y.T.; Li, C.C.; Lei, M.Z.; Li, G.

    2010-01-01

    Remote handling technology, especially the flexible in-vessel inspection system (FIVIS) without breaking the working condition of the vacuum vessel, has been identified as one major challenge on the maintenance for the future tokamak fusion reactor. The FIVIS introduced here is specially developed for EAST superconducting tokamak that has actively cooled plasma facing components (PFCs). It aims flexible close-up inspection of EAST PFCs to help the understanding of operation issues that could occur in the vacuum vessel. This paper resumes the preliminary work of the FIVIS project, including the requirement analysis and the development of the conceptual design. The FIVIS consists out of a long reach multi-articulated manipulator and a process tool. The manipulator has a modular design for its subsystems and can reach all areas of the first wall in the distance of 15 mm and in the range of ±90 o along toroidal direction. It will be folded and hidden in the designated horizontal port during plasma discharge period.

  12. 37Ar monitoring techniques and on-site inspection system

    International Nuclear Information System (INIS)

    Duan Rongliang; Chen Yinliang; Li Wei; Wang Hongxia; Hao Fanhua

    2001-01-01

    37 Ar is separated, purified and extracted from air sample with a low temperature gas-solid chromatographic purifying method, prepared into a radioactive measurement source and its radioactivity is measured with a proportional counter. Based on the monitoring result, a judgement can be made if an nuclear explosion event has happened recently in a spectabilis area. A series of element techniques that are associated the monitoring of the trace element 37 Ar have been investigated and developed. Those techniques include leaked gas sampling, 37 Ar separation and purification, 37 Ar radioactivity measurement and the on-site inspection of 37 Ar. An advanced 37 Ar monitoring method has been developed, with which 200 liters of air can be treated in 2 hours with sensitivity of 0.01 Bq/L for 37 Ar radioactivity measurement. A practical 37 Ar On-site Inspection system has been developed. This research work may provide technical and equipment support for the verification protection, verification supervision and CTBT verification

  13. Risk evaluation system for operational events and inspection findings

    International Nuclear Information System (INIS)

    Lopez G, A.; Godinez S, V.; Lopez M, R.

    2010-10-01

    The Mexican Nuclear Regulatory Commission has developed an adaptation of the US NRC Significance Determination Process (SDP) to evaluate the risk significance of operational events and inspection findings in Laguna Verde nuclear power plant. The Mexican Nuclear Regulatory Commission developed a plant specific flow chart for preliminary screening instead of the open questionnaire used by the US NRC-SDP, with the aim to improve the accuracy of the screening process. Also, the work sheets and support information tables required by the SDP were built up in an Excel application which allows to perform the risk evaluation in an automatic way, focusing the regulator staff efforts in the risk significance analysis instead of the risk calculation tasks. In order to construct this tool a simplified PRA model was developed and validated with the individual plant examination model. This paper shows the Mexican Nuclear Regulatory Commission process and some risk events evaluations performed using the Risk Evaluation System for Operational Events and Inspection Findings (SERHE, by its acronyms in Spanish). (Author)

  14. 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

  15. Support system for welded part inspection using X-ray. Simplified inspection system which does not need skilled workers

    International Nuclear Information System (INIS)

    Suga, Yasuo

    1995-01-01

    X-ray radiography has the excellent ability for operation and recording, accordingly, it has been used widely in industrial fields, but for deciding the presence of defects and their kinds and shapes from X-ray films, skilled workers are required. Recently because of the shortage of skilled workers and the increase of inspection efficiency, the necessity of its automation increased. The images of the films of the X-ray inspection of welded part are photographed with a CCD camera, and these are taken in a personal computer as the image data, then image processing is applied to them, and defect images are extracted automatically. Further, the technique of displaying the images so that inspectors can recognize them easily is devised. These procedures were examined. The constitution of the system the way of thinking in developing the system, the acquiring of high contrast images, the emphasis of defect images, the elimination of noise the treatment of emphasizing nuclear defect images, the elimination of background and the extraction of defect images, the results of the processing and image display are reported. The order of processes, the kind of a filter used and so on can be changed according to the purpose, the kind of welding and the image quality of films. (K.I.)

  16. DESIGN OF A WELDING AND INSPECTION SYSTEM FOR WASTE STORAGE CLOSURE

    International Nuclear Information System (INIS)

    H.B. Smartt; A.D. Watkins; D.P. Pace; R.J. Bitsoi; E.D. Larsen T.R. McJunkin; C.R. Tolle

    2005-01-01

    This work reported here was done to provide a conceptual design for a robotic welding and inspection system for the Yucca Mountain Repository waste package closure system. The welding and inspection system is intended to make the various closure welds that seal and/or structurally join the lids to the waste package vessels. The welding and inspection system will also perform surface and volumetric inspections of the various closure welds and has the means to repair closure welds, if required. The system is designed to perform these various activities remotely, without the necessity of having personnel in the closure cell

  17. Fast and Accurate Non-destructive Testing System for Inspection of Canning Tubes

    DEFF Research Database (Denmark)

    Gundtoft, Hans Erik; Nielsen, E.

    1973-01-01

    The authors describe the development of an inspection bench for the non-destructive examination of canning tubes. The bench is original in that the internal diameter is calculated from exact measurement of the outer diameter and the wall thickness. The transducers for inspection and control are r...

  18. 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

  19. 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)

  20. A development methodology for a remote inspection system with JAVA and socket

    International Nuclear Information System (INIS)

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

    2004-01-01

    We have developed RISYS (Reactor Inspection System) which inspects reactor vessel welds by an underwater mobile robot. The system consists of a main control computer and an inspection robot which is controlled by the main control computer. Since the environments of the inspection tasks in a nuclear plant, like in other industrial fields, is very poor, serious accidents often happen. Therefore the necessity for remote inspection and control system has increased more and more. We have carried out the research for a remote inspection model for RISYS, and have adopted the world wide web, java, and socket technologies for it. Client interface to access the main control computer that controls the inspection equipment is essential for the development of a remote inspection system. It has been developed with a traditional programming language, for example, Visual C++, Visual Basic and X-Window. However, it is too expensive to vend and maintain the version of a interface program because of the different computer O/S. Nevertheless web and java technologies come to the fore to solve the problems but the java interpreting typed language could incur a performance problem in operating the remote inspection system. We suggest a methodology for developing a remote inspection system with java, a traditional programming language, and a socket programming that solves the java performance problem in this paper

  1. Inspection technologies -Development of national safeguards technology-

    International Nuclear Information System (INIS)

    Hong, J. S.; Kim, B. K.; Kwack, E. H.

    1996-12-01

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

  2. Remote handling and robotic inspections of Palo Verde reactor vessel internals

    International Nuclear Information System (INIS)

    Ryder, W.

    1998-01-01

    Remote visual examinations and handling evolutions in high radiation field environments have required the use of radiation tolerant video systems. These systems involve significant expense and potentially require large envelope deployment structures. Recent events at Palo Verde including Upper Guide Structure damage and Reactor Vessel In-Service Inspections have provided opportunities for research, design and utilization of alternative approaches. Most significant of these, utilization of CCD modules with high magnification capabilities, have produced higher quality viewing, reduced maintenance expenditures, and rapid deployment intervals. (orig.) [de

  3. Non-periodic inspection optimization of multi-component and k-out-of-m systems

    International Nuclear Information System (INIS)

    Hajipour, Yassin; Taghipour, Sharareh

    2016-01-01

    This paper proposes a model to find the optimal non-periodic inspection interval over a finite planning horizon for two types of multi-component repairable systems. The first system contains hard-type and soft-type components, and the second system is a k-out-of-m system with m identical components. The failures of components in both systems follow a non-homogeneous Poisson process. A component can be a single part such as battery or line cord, or a subsystem, such as circuit breaker or charger in an infusion pump, which depending on their failures could be either replaced or minimally repaired according to their ages at failure. The systems are inspected at scheduled inspections or when an event of opportunistic inspection or a system failure occur. We develop a model to find the optimal inspection scheme for each system, which results in the minimum total expected cost over the system's lifecycle. We first develop a simulation model to obtain the total expected cost for a given non-periodic inspection scheme, and then integrate the simulation model with a genetic algorithm to obtain the optimal scheme more efficiently. - Highlights: • Non-periodic inspection optimization of two complex systems. • One system consists of soft-type and hard-type components. • The second system is a k-out-of-m system. • Integration of a simulation model and the genetic algorithm. • The model can be used when inspection is challenging or costly.

  4. 15 CFR 740.11 - Governments, international organizations, and international inspections under the Chemical...

    Science.gov (United States)

    2010-01-01

    ... INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE EXPORT ADMINISTRATION REGULATIONS LICENSE EXCEPTIONS § 740.11... Bureau of Industry and Security. (b) Governments—(1) Scope. The provisions of paragraph (b) authorize..., Korea (Republic of), New Zealand, Singapore, Sweden, Switzerland, and Taiwan. (c) International...

  5. INETEC new system for inspection of PWR reactor pressure vessel head

    International Nuclear Information System (INIS)

    Nadinic, B.; Postruzin, Z.

    2004-01-01

    INETEC Institute for Nuclear Technology developed new equipment for inspection of PWR and VVER reactor pressure vessel head. The new advances in inspection technology are presented in this article, as the following: New advance manipulator for inspection of RPVH with high speed of inspection possibilities and total automated work; New sophisticated software for manipulator driving which includes 3D virtual presentation of manipulator movement and collision detection possibilities; New multi axis controller MAC-8; New end effector system for inspection of penetration tube and G weld; New eddy current and ultrasonic probes for inspection of G weld and penetration tube; New Eddy One Raster scan software for analysis of eddy current data with mant advanced features which allows easy and quick data analysis. Also the results of laboratory testing and laboratory qualification are presented on reactor pressure vessel head mock, as well as obtained speed of inspection and quality of collected data.(author)

  6. Integrating design and production planning with knowledge-based inspection planning system

    International Nuclear Information System (INIS)

    Abbasi, Ghaleb Y.; Ketan, Hussein S.; Adil, Mazen B.

    2005-01-01

    In this paper an intelligent environment to integrate design and inspection earlier to the design stage. A hybrid knowledge-based approach integrating computer-aided design (CAD) and computer-aided inspection planning (CAIP) was developed, thereafter called computer-aided design and inspection planning (CADIP). CADIP was adopted for automated dimensional inspection planning. Critical functional features were screened based on certain attributes for part features for inspection planning application. Testing the model resulted in minimizing the number of probing vectors associated with the most important features in the inspected prismatic part, significant reduction in inspection costs and release of human labor. In totality, this tends to increase customer satisfaction as a final goal of the developed system. (author)

  7. Design of database management system for 60Co container inspection system

    International Nuclear Information System (INIS)

    Liu Jinhui; Wu Zhifang

    2007-01-01

    The function of the database management system has been designed according to the features of cobalt-60 container inspection system. And the software related to the function has been constructed. The database querying and searching are included in the software. The database operation program is constructed based on Microsoft SQL server and Visual C ++ under Windows 2000. The software realizes database querying, image and graph displaying, statistic, report form and its printing, interface designing, etc. The software is powerful and flexible for operation and information querying. And it has been successfully used in the real database management system of cobalt-60 container inspection system. (authors)

  8. Analysis of grease contamination influence on the internal radial clearance of ball bearings by thermographic inspection

    Directory of Open Access Journals (Sweden)

    Mišković Žarko Z.

    2016-01-01

    Full Text Available One of the most important factors influencing ball bearings service life is its internal radial clearance. However, this parameter is also very complex because it depends on applied radial load and ball bearings dimensions, surface finish and manufacturing materials. Thermal condition of ball bearings also significantly affects internal radial clearance. Despite many researches performed in order to find out relevant facts about different aspects of ball bearings thermal behaviour, only few of them are dealing with the real working conditions, where high concentration of solid contaminant particles is present. That’s why the main goal of research presented in this paper was to establish statistically significant correlation between ball bearings temperatures, their working time and concentration of contaminant particles in their grease. Because of especially difficult working conditions, the typical conveyor idlers bearings were selected as representative test samples and appropriate solid particles from open pit coal mines were used as artificial contaminants. Applied experimental methodology included thermographic inspection, as well as usage of custom designed test rig for ball bearings service life testing. Finally, by obtained experimental data processing in advanced software, statistically significant mathematical correlation between mentioned bearings characteristics was determined and applied in commonly used internal radial clearance equation. That is the most important contribution of performed research - the new equation and methodology for ball bearings internal clearance determination which could be used for eventual improvement of existing bearings service life equations. [Projekat Ministarstva nauke Republike Srbije, br. TR35029 i br. TR14033

  9. Transfer system development for a remote inspection robot in nuclear power plants

    International Nuclear Information System (INIS)

    Mizuno, M.; Ohnuma, M.; Hamada, K.; Mizutani, T.; Shimada, A.; Segawa, M.; Kubo, K.

    1984-01-01

    A remote operated robot system has been developed for inspection inside the primary containment vessel (PCV) of nuclear power plants. This system consists of an inspection vehicle, a monorail driving system, a signal transmission system, a power supply system and an operator console.. The system has two main features. First is that the operator can transfer the vehicle at any time from outside the PCV to inside or vice versa through a personnel airlock. The second feature is that the vehicle can be transported from one inspection route to another route at junction points. A prototype inspection robot system was fabricated on a trial basis. Running and inspection performances were confirmed utilizing actual size test apparatus

  10. An automatic chip structure optical inspection system for electronic components

    Science.gov (United States)

    Song, Zhichao; Xue, Bindang; Liang, Jiyuan; Wang, Ke; Chen, Junzhang; Liu, Yunhe

    2018-01-01

    An automatic chip structure inspection system based on machine vision is presented to ensure the reliability of electronic components. It consists of four major modules, including a metallographic microscope, a Gigabit Ethernet high-resolution camera, a control system and a high performance computer. An auto-focusing technique is presented to solve the problem that the chip surface is not on the same focusing surface under the high magnification of the microscope. A panoramic high-resolution image stitching algorithm is adopted to deal with the contradiction between resolution and field of view, caused by different sizes of electronic components. In addition, we establish a database to storage and callback appropriate parameters to ensure the consistency of chip images of electronic components with the same model. We use image change detection technology to realize the detection of chip images of electronic components. The system can achieve high-resolution imaging for chips of electronic components with various sizes, and clearly imaging for the surface of chip with different horizontal and standardized imaging for ones with the same model, and can recognize chip defects.

  11. Promoting radiation protection and safety for X-ray inspection systems

    International Nuclear Information System (INIS)

    Maharaj, Harri P.

    2008-01-01

    This paper aims to present a regulatory perspective on radiation protection and safety relevant to facilities utilizing baggage X-ray inspection systems. Over the past several years there has been rapid growth in the acquisition and utilization of X-ray tube based inspection systems for security screening purposes worldwide. In addition to ensuring compliance with prescribed standards applicable to such X-ray systems, facilities subject to federal jurisdiction in Canada are required to comply with established codes of practice, which, not only are in accordance with occupational health and safety legislation but also are consistent with international guidance. Overall, these measures are aimed at reducing radiation risks and adverse health effects. Data, acquired in the past several years in a number of facilities through various instruments, namely, monitoring and surveillance, radiation safety audits, onsite evaluations, device registration processes and information developed, were considered in conjunction with detrimental traits. Changes are necessary to reduce radiation and safety risks from both an ALARA point of view and an accountability perspective. Establishing, developing, implementing and following a radiation protection program is warranted and advocated. Minimally, such a program shall be managed by a radiation safety officer. It shall promote and sustain a radiation safety culture in the workplace; shall ensure properly qualified individuals operate and service the X-ray systems in accordance with established and authorized procedures; and shall incorporate data recording and life cycle management principles. Such a program should be the norm for a facility that utilizes baggage X-ray inspection systems for security purposes, and it shall be subject to continuous regulatory oversight. (author)

  12. Markov counting and reward processes for analysing the performance of a complex system subject to random inspections

    International Nuclear Information System (INIS)

    Ruiz-Castro, Juan Eloy

    2016-01-01

    In this paper, a discrete complex reliability system subject to internal failures and external shocks, is modelled algorithmically. Two types of internal failure are considered: repairable and non-repairable. When a repairable failure occurs, the unit goes to corrective repair. In addition, the unit is subject to external shocks that may produce an aggravation of the internal degradation level, cumulative damage or extreme failure. When a damage threshold is reached, the unit must be removed. When a non-repairable failure occurs, the device is replaced by a new, identical one. The internal performance and the external damage are partitioned in performance levels. Random inspections are carried out. When an inspection takes place, the internal performance of the system and the damage caused by external shocks are observed and if necessary the unit is sent to preventive maintenance. If the inspection observes minor state for the internal performance and/or external damage, then these states remain in memory when the unit goes to corrective or preventive maintenance. Transient and stationary analyses are performed. Markov counting and reward processes are developed in computational form to analyse the performance and profitability of the system with and without preventive maintenance. These aspects are implemented computationally with Matlab. - Highlights: • A multi-state device is modelled in an algorithmic and computational form. • The performance is partitioned in multi-states and degradation levels. • Several types of failures with repair times according to degradation levels. • Preventive maintenance as response to random inspection is introduced. • The performance-profitable is analysed through Markov counting and reward processes.

  13. Ultrasonic inspection method and system for detection of steeple cracking in turbine disk rims

    International Nuclear Information System (INIS)

    Birring, A.S.; Lamping, G.A.; Van der Veer, W.R.; Hanley, J.J.

    1990-01-01

    Steam turbine disks which operate under high cyclic stress in a moist environment can develop cracks in the disk-rim steeples. Detection of these cracks using nondestructive testing methods is necessary to assure safe operation and avoid unnecessary disk replacement. Both magnetic particle (MT) and ultrasonic testing (UT) can be used to inspect the steeples; however, UT can be used without removing the blades. A system for inspecting bladed steeples has been developed that can be applied on a range of disks including those in Westinghouse, General Electric, and Allis Chalmers turbines. The system performs an inspection as the turbine is rotated at slow speeds over turning rolls. This procedure greatly reduces inspection time because the inspection can be done without deblading the disk or resetting the inspection equipment for different rim segments

  14. Development of the Macro Command Editing Executive System for Factory Workers-Oriented Programless Visual Inspection System

    Science.gov (United States)

    Anezaki, Takashi; Wakitani, Kouichi; Nakamura, Masatoshi; Kubo, Hiroyasu

    Because visual inspection systems are difficult to tune, they create many problems for the kaizen process. This results in increased development costs and time to assure that the inspection systems function properly. In order to improve inspection system development, we designed an easy-tuning system called a “Program-less” visual inspection system. The ROI macro command which consisted of eight kinds of shape recognition macro commands and decision, operation, control commands was built. Furthermore, the macro command editing executive system was developed by the operation of only the GUI without editing source program. The validity of the ROI macro command was proved by the application of 488 places.

  15. Implementation of the Air Program Information Management System (APIMS) Inspection Module

    Science.gov (United States)

    2009-05-01

    7 5 T H A I R B A S E W I N G Implementation of the Air Program Information Management System (APIMS) Inspection Module 2009 Environment...Implementation of the Air Program Information Management System (APIMS) Inspection Module 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER

  16. The convertible client/server technology in large container inspection system

    International Nuclear Information System (INIS)

    Chen Zhiqiang; Zhang Li; Gao Wenhuan; Kang Kejun

    2001-01-01

    The author presents a new convertible client/server technology in distributed networking environment of a large container inspection system. The characteristic and advantage of this technology is introduced. The authors illustrate the policy of the technology to develop the networking program, and provide one example about how to program the software in large container inspection system using the new technology

  17. Evaluating physical protection systems of licensed nuclear facilities using systems engineered inspection guidance

    International Nuclear Information System (INIS)

    Bradley, R.T.; Olson, A.W.; Rogue, F.; Scala, S.; Richard, E.W.

    1980-01-01

    The Lawrence Livermore National Laboratory (LLNL) and the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) have applied a systems engineering approach to provide the NRC Office of Inspection and Enforcement (IE) with improved methods and guidance for evaluating the physical protection systems of licensed nuclear facilities

  18. A Laser Metrology/Viewing System for ITER In-Vessel Inspection

    International Nuclear Information System (INIS)

    Spampinato, P.T.; Barry, R.E.; Chesser, J.B.; Menon, M.M.; Dagher, M.A.; Slotwinski, A.

    1997-10-01

    This paper identifies the requirements for a remotely operated precision laser ranging system for the International Thermonuclear Experimental Reactor. The inspection system is used for metrology and viewing, and must be capable of achieving submillimeter accuracy and operation in a reactor vessel that has high gamma radiation, high vacuum, elevated temperature, and magnetic field levels. A coherent, frequency modulated laser radar system is under development to meet these requirements. The metrology/viewing sensor consists of a compact laser-optic module linked through fiberoptics to the laser source and imaging units, located outside the harsh environment. The deployment mechanism is a remotely operated telescopic mast. Gamma irradiation up to 10 7 Gy was conducted on critical sensor components with no significant impact to data transmission, and analysis indicates that critical sensor components can operate in a magnetic field with certain design modifications. Plans for testing key components in a magnetic field are underway

  19. Radiation safety for baggage x-ray inspection systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-05-01

    This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs.

  20. Radiation safety for baggage x-ray inspection systems

    International Nuclear Information System (INIS)

    1994-05-01

    This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs

  1. Preliminary conceptual design of inspection and maintenance for KALIMER reactor system

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Young Sang; Kim, Seok Hun; Yoo, Bong

    2000-08-01

    In-service inspection and maintenance are very important for improving the safety and availability of nuclear power plants. The conceptual requirements of in-service inspection and maintenance should be reflected in the earlier design process for the verification of the plant operability and reliability. In this report the fundamental approaches of the inspection and maintenance for KALIMER are established to ensure the structural integrity and operability for KALIMER. The general strategy and methodology of maintenance and inspection for the reactor system and components are proposed and described for satisfying the intents of the section XI, division 3, of ASME code and considering the design characteristics of KALIMER.

  2. 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

  3. Improvement of visualization efficiency for the nondestructive inspection image of internal defects in plate type nuclear fuel

    International Nuclear Information System (INIS)

    Park, Seung Kyu; Park, Nak Kyu; Baik, Sung Hoon; Lee, Yoon Sang; Cheong, Yong Moo; Kang, Young June

    2012-01-01

    Plate type nuclear fuel has been adopted in most research reactors. The production quality of the fuel is a key part for an efficient and stable generation of thermal energy in research reactors. Thus, a nondestructive quality inspection for the internal defects of plate type nuclear fuel is a key process during the production of nuclear fuel for safety insurance. Nondestructive quality inspections based on X rays and ultrasounds have been widely used for the defect detection of plate type nuclear fuel. X ray testing is a simple and fast inspection method, and provides an image in real time as the inspection results. Thus, the testing can be carried out by a non expert field worker. However, it is hard to detect closed type defects that should be detected during the production of plate type nuclear fuel. Ultrasonic testing is a powerful tool to detect internal defects including open type and closed type defects in plate type nuclear fuel. However, the inspection process is complicated because an immersion test should be carried out in a water tank. It is also a time consuming inspection method because area testing to acquire image is based on the scanning of the point by point inspections. Among nondestructive inspection techniques, the techniques based on laser interferometry and infrared thermography have been widely used in the detection of internal defects of plate type composite materials, such as aircraft, automotive etc. While infrared thermography technique (IRT) analyses the thermal behavior of the specimen surface, laser interferometry technique (LIT) analyses the deformation field. Both techniques are useful tools for detection and evaluation of internal defects in composite materials. Especially, the laser interferometry technique can provide the depth information of internal defects. Laser interferometry technique (LIT) is a non contact inspection method faster than thermography. Also, this technique requires less energy than thermography and the

  4. 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

  5. The World Bank Inspection Panel and Quasi-Judicial Oversight: In Search of the 'Judicial Spirit' in Public International Law

    NARCIS (Netherlands)

    A. Naudé Fourie (Andria)

    2009-01-01

    textabstractThis PhD dissertation conceptualizes the World Bank Inspection Panel as a mechanism of quasi-judicial review or oversight, aimed at enhancing the accountability and legitimacy of the World Bank – which is conceived as an international institution exercising public power. The author

  6. Conclusions with regard to the inspection goals of a system of material balance areas

    International Nuclear Information System (INIS)

    Gladitz, J.

    1989-01-01

    Starting from IAEA inspection goals in the control of individual material balance area, procedures of computation and estimation of inspection goals are derived for a system of material balance areas allowing for an optimal diversion strategy. By it the prerequisites were also developed to an evaluation of these goals for a State as a whole. (author)

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

    International Nuclear Information System (INIS)

    Furukawa, Masami; Shimizu, Kazuaki; Hiruta, Toshihito; Mizugaki, Toshio; Ohi, Yoshihiro; Chida, Tooru.

    1994-10-01

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

  8. 48 CFR 552.246-70 - Source Inspection by Quality Approved Manufacturer.

    Science.gov (United States)

    2010-10-01

    ...) Inspection system and inspection of facilities. (1) The inspection system maintained by the Contractor under... Federal Standard 368 or the International Organization for Standardization (ISO) Standard 9001:2000 (Quality Management Systems—Requirements). A documented description of the inspection system shall be made...

  9. Scanning Ultrasonic Spectroscopy System Developed for the Inspection of Composite Flywheels

    Science.gov (United States)

    Martin, Richard E.; Baaklini, George Y.

    2002-01-01

    Composite flywheels are being considered as replacements for chemical batteries aboard the International Space Station. A flywheel stores energy in a spinning mass that can turn a generator to meet power demands. Because of the high rotational speeds of the spinning mass, extensive testing of the flywheel system must be performed prior to flight certification. With this goal in mind, a new scanning system has been developed at the NASA Glenn Research Center for the nondestructive inspection of composite flywheels and flywheel subcomponents. The system uses ultrasonic waves to excite a material and examines the response to detect and locate flaws and material variations. The ultrasonic spectroscopy system uses a transducer to send swept-frequency ultrasonic waves into a test material and then receives the returning signal with a second transducer. The received signal is then analyzed in the frequency domain using a fast Fourier transform. A second fast Fourier transform is performed to examine the spacing of the peaks in the frequency domain. The spacing of the peaks is related to the standing wave resonances that are present in the material because of the constructive and destructive interferences of the waves in the full material thickness as well as in individual layers within the material. Material variations and flaws are then identified by changes in the amplitudes and positions of the peaks in both the frequency and resonance spacing domains. This work, conducted under a grant through the Cleveland State University, extends the capabilities of an existing point-by-point ultrasonic spectroscopy system, thus allowing full-field automated inspection. Results of an ultrasonic spectroscopy scan of a plastic cylinder with intentionally seeded flaws. The result of an ultrasonic spectroscopy scan of a plastic cylinder used as a proof-of-concept specimen is shown. The cylinder contains a number of flat bottomed holes of various sizes and shapes. The scanning system

  10. 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.

  11. 49 CFR 213.333 - Automated vehicle inspection systems.

    Science.gov (United States)

    2010-10-01

    ... applied (pounds). c = Coefficient of friction between rail/tie which is assigned a nominal value of (0.4... hours of the inspection, output reports that— (1) Provide a continuous plot, on a constant-distance axis... exception report containing a systematic listing of all track geometry conditions which constitute an...

  12. Unique systems for inspection and repair of VVER steam generators

    International Nuclear Information System (INIS)

    Kovalyk, Adrian; Pilat, Peter; Jablonicky, Pavol

    2014-01-01

    During over 30 years, VUJE Trnava has developed a series of remote control manipulators for in-service inspection and maintenance of steam generator collectors. The manipulators have been widely used on WWER type reactors in Slovakia and abroad. Some of the manipulators for non-destructive testing are shown.

  13. Measurement system analysis for binary inspection: Continuous versus dichotomous measurands

    NARCIS (Netherlands)

    de Mast, J.; Erdmann, T.P.; van Wieringen, W.N.

    2011-01-01

    We review methods for assessing the reliability of binary measurements, such as accept/reject inspection in industry. Our framework introduces two factors that are highly relevant in deciding which method to use: (1) whether a reference value (gold standard) can be obtained and (2) whether the

  14. Image acquisition, transmission and assignment in 60Co container inspection system

    International Nuclear Information System (INIS)

    Wu Zhifang; Zhou Liye; Liu Ximing; Wang Liqiang

    1999-01-01

    The author describes the data acquisition mode and image reconstruction method in 60 Co container inspection system, analyzes the relationship between line pick period and geometry distortion, makes clear the demand to data transmitting rate. It discusses several data communication methods, draws up a plan for network, realizes automatic direction and reasonable assignment of data in the system, cooperation of multi-computer and parallel processing, thus greatly improves the systems inspection efficiency

  15. A real-time surface inspection system for precision steel balls based on machine vision

    Science.gov (United States)

    Chen, Yi-Ji; Tsai, Jhy-Cherng; Hsu, Ya-Chen

    2016-07-01

    Precision steel balls are one of the most fundament components for motion and power transmission parts and they are widely used in industrial machinery and the automotive industry. As precision balls are crucial for the quality of these products, there is an urgent need to develop a fast and robust system for inspecting defects of precision steel balls. In this paper, a real-time system for inspecting surface defects of precision steel balls is developed based on machine vision. The developed system integrates a dual-lighting system, an unfolding mechanism and inspection algorithms for real-time signal processing and defect detection. The developed system is tested under feeding speeds of 4 pcs s-1 with a detection rate of 99.94% and an error rate of 0.10%. The minimum detectable surface flaw area is 0.01 mm2, which meets the requirement for inspecting ISO grade 100 precision steel balls.

  16. Documentation for first annual testing and inspections of Benificial Uses Shipping System (BUSS) Cask

    International Nuclear Information System (INIS)

    Lundeen, J.E.

    1994-01-01

    The purpose of this report is to compile date generated during the first annual tests and inspections of the Benificiai Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in chapter 8 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. Section 8.2 ''Maintenance and Periodic Inspection Program'' of the BUSS Cask SARP requires that the following tests and inspections be performed on an annual basis: Hydrostatic pressure test; helium leak test; dye penetrant test on the trunnions and lifting lugs; and torque test on all bolts; impact limiter inspection and weight test. The first annual inspections and testing of the BUSS Cask were completed on May 5, 1994, and met the SARP criteria

  17. In-service inspections of the reactor cooling system of pressurized water reactors

    International Nuclear Information System (INIS)

    Fuerste, W.; Hohnerlein, G.; Werden, B.

    1982-01-01

    In order to guarantee constant safety of the components of the reactor cooling system, regular in-service inspections are carried out after commissioning of the nuclear power plant. This contribution is concerned with the components of the reactor cooling system, referring to the legal requirements, safety-related purposes and scope of the in-service inspections during the entire period of operation of a nuclear power plant. Reports are made with respect to type, examination intervals, examination technique, results and future development. The functional tests which are carried out within the scope of the in-service inspections are not part of this contribution. (orig.) [de

  18. Development of video probe system for inspection of feeder pipe support in calandria reactor

    International Nuclear Information System (INIS)

    Cho, Jai Wan; Lee, Nam Ho; Choi, Young Soo

    2000-07-01

    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 untrasonic 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 impossible to inspect feederpipe support area thoroughlv because of narrow and confined accessibility, that is, an inspection space between the pressure tube channels is less than 100mm 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 feederpipe 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

  19. A remote telepresence robotic system for inspection and maintenance of a nuclear power plant

    International Nuclear Information System (INIS)

    Crane, C.D. III; Tulenko, J.S.

    1993-01-01

    Progress in reported in the areas of environmental hardening; database/world modeling; man-machine interface; development of the Advanced Liquid Metal Reactor (ALMR) maintenance inspection robot design; and Articulated Transporter/Manipulator System (ATMS) development

  20. Simulating an Isochronal Scheduled Inspection System for the P-3 Orion

    National Research Council Canada - National Science Library

    Jones, Jeffrey

    1998-01-01

    ...) for the United States Navy's P-3 Orion. Implementation of ISIS, which is based solely upon calendar time, has been proposed to replace the present system of scheduled inspections that are based upon both calendar time and flight hours...

  1. Development of intelligent Eddy Current Testing (ECT) system for PWR steam generator tube inspection

    International Nuclear Information System (INIS)

    Kawata, K.; Kawase, N.; Kurokawa, M.; Asada, Y.

    2005-01-01

    The intelligent ECT system was developed for the inspection of heat transfer tubes of the steam generator of the PWR plant. It consists of intelligent probe, data acquisition unit and data analysis system. The probe combines 24 channels inclined lay out drive coils and thin film pick-up coils with built-in electric circuits to provide high inspection capability equivalent to rotating coil ECT and high-speed inspection equivalent to conventional bobbin coil ECT. The advanced data analysis system that has filtering and automatic analysis functions is also developed to enable fast and precise analysis of large volume inspection data. The system was qualified by confirmation tests in FY 2003 to show thinned thickness sizing accuracy within ± 5%. (T. Tanaka)

  2. 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

  3. Canning and inspection system for nuclear reactor fuel and reflector elements

    International Nuclear Information System (INIS)

    Goldman, L.A.; Hawke, B.C.

    1980-01-01

    A system is disclosed for canning, inspecting and transferring to a storage area fuel and reflector elements from a nuclear reactor. The system includes a transfer chute, environmental chamber, conveyor and canning mechanism operative to remove and replace closures on containers into which fuel and reflector elements are inserted or from which stored elements are removed while maintaining a sealed gaseous environment and permitting visual and mechanical inspection of the elements by an operator located in a remote shielded area

  4. Development of sup 6 sup 0 Co cargo train inspection system

    CERN Document Server

    Wu Zhi Fang

    2002-01-01

    The author introduces the research and development of sup 6 sup 0 Co cargo train inspection system. With the use of radiography principle, every car image is acquired when the cargo train runs through the inspection channel. It is evaluated whether the cargo in car matches the corresponding customs declaration information with digital image processing techniques. The system has been installed in railway port at Manzhouli Customs

  5. Comparison of secondary system piping Cr content with inspection data

    International Nuclear Information System (INIS)

    Tapping, R.L.; Mitchell, A.M.

    1997-06-01

    For several years a number of Ontario Hydro and CANDU-6 stations have been sampling sections of secondary-side piping for chromium content. Several hundred of these measurements have been made, and comparisons with inspection data drawn. There is special interest in chromium concentrations in the range 0.01< Cr<0.1 wt.%, in order to better define the effect of trace chromium content on susceptibility to flow-assisted corrosion. (author)

  6. Image processing in 60Co container inspection system

    International Nuclear Information System (INIS)

    Wu Zhifang; Zhou Liye; Wang Liqiang; Liu Ximing

    1999-01-01

    The authors analyzes the features of 60 Co container inspection image, the design of several special processing methods for container image and some normal processing methods for two-dimensional digital image, including gray enhancement, pseudo-enhancement, space filter, edge enhancement, geometry process, etc. It gives out the way to carry out the above mentioned process in Windows 95 or Win NT. It discusses some ways to improve the image processing speed on microcomputer and good results were obtained

  7. An intelligent system for real time automatic defect inspection on specular coated surfaces

    Science.gov (United States)

    Li, Jinhua; Parker, Johné M.; Hou, Zhen

    2005-07-01

    Product visual inspection is still performed manually or semi automatically in most industries from simple ceramic tile grading to complex automotive body panel paint defect and surface quality inspection. Moreover, specular surfaces present additional challenge to conventional vision systems due to specular reflections, which may mask the true location of objects and lead to incorrect measurements. There are some sophisticated visual inspection methods developed in recent years. Unfortunately, most of them are highly computational. Systems built on those methods are either inapplicable or very costly to achieve real time inspection. In this paper, we describe an integrated low-cost intelligent system developed to automatically capture, extract, and segment defects on specular surfaces with uniform color coatings. The system inspects and locates regular surface defects with lateral dimensions as small as a millimeter. The proposed system is implemented on a group of smart cameras using its on-board processing ability to achieve real time inspection. The experimental results on real test panels demonstrate the effectiveness and robustness of proposed system.

  8. Designs for remote inspection of the ALMR Reactor Vessel Auxiliary Cooling System (RVACS)

    International Nuclear Information System (INIS)

    Sweeney, F.J.; Carroll, D.G.; Chen, C.; Crane, C.; Dalton, R.; Taylor, J.R.; Tosunoglu, S.; Weymouth, T.

    1993-01-01

    One of the most important safety systems in General Electric's (GI) Advanced Liquid Metal Reactor (ALMR) is the Reactor Vessel Auxiliary Cooling System (RVACS). Because of high temperature, radiation, and restricted space conditions, GI desired methods to remotely inspect the RVACS, emissive coatings, and reactor vessel welds during normal refueling operations. The DOE/NE Robotics for Advanced Reactors program formed a team to evaluate the ALMR design for remote inspection of the RVACS. Conceptual designs for robots to perform the required inspection tasks were developed by the team. Design criteria for these remote systems included robot deployment, power supply, navigation, environmental hardening of components, tether management, communication with an operator, sensing, and failure recovery. The operation of the remote inspection concepts were tested using 3-D simulation models of the ALMR. In addition, the team performed an extensive technology review of robot components that could survive the environmental conditions in the RVACS

  9. Proceedings of the international workshop on conduct of inspections and inspector qualification and training

    International Nuclear Information System (INIS)

    Grimes, B.K.

    1993-02-01

    In the Fall of 1991, the OECD Committee on Nuclear Regulatory Activities (CNRA) approved the proposal of the Working Group (WGIP) on Inspection Practices to hold a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the USNRC in Chattanooga, Tennessee. The workshop was held from August 29 to September 4, 1992. The workshop was preceded by an orientation briefing for facilitators and a get-acquainted reception for participants. The workshop began with a plenary introductory session and ended with a plenary conclusion and evaluation session. Individual discussion sessions have been cataloged separately

  10. Application of 4-Face Fuel Visual Inspection System during Outage in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shin, J. C.; Kim, J. I.; Choi, C. B.; Kim, Y. C.; Kang, C. B.

    2008-01-01

    Recently, as a measure to reduce an outage duration in nuclear power plants (NPPs), a four-face fuel visual inspection system (4-FFVIS) built in 4 cameras was introduced by Ahlberg Electronics, Sweden. The 4- FFVIS is used to inspect the external appearance of irradiated fuel assemblies in order to confirm their integrity against mechanical defects and foreign materials. Until now, however, a typical one-face fuel inspection system(1-FFVIS) has been world-widely utilized in NPPs. The 1-FFVIS requires four turns with 90 degree to inspect every face of the fuel assembly, causing a relatively long inspecting time. But the 4- FFVIS allow us to inspect every face of the fuel assembly at the same time. The inspection time with the 4-FFVIS may be less than two minutes per fuel assembly, whereas that with the 1-FFVIS is about six minutes per fuel assembly. In viewpoint of this merit, the 4-FFVIS is expected to be world-widely used in the near future. In this paper, the technical requirements necessary to develop the 4-FFVIS as well as some improvements to complement the current 4-FFVIS are described

  11. International EMS Systems

    DEFF Research Database (Denmark)

    Langhelle, Audun; Lossius, Hans Morten; Silfvast, Tom

    2004-01-01

    exist, however, especially within the ground and air ambulance service, and the EMS systems face several challenges. Main problems and challenges emphasized by the authors are: (1) Denmark: the dispatch centres are presently not under medical control and are without a national criteria based system......Emergency medicine service (EMS) systems in the five Nordic countries have more similarities than differences. One similarity is the involvement of anaesthesiologists as pre-hospital physicians and their strong participation for all critically ill and injured patients in-hospital. Discrepancies do....... Access to on-line medical advice of a physician is not available; (2) Finland: the autonomy of the individual municipalities and their responsibility to cover for primary and specialised health care, as well as the EMS, and the lack of supporting or demanding legislation regarding the EMS; (3) Iceland...

  12. Mechanized ultrasonic inspection of austenitic pipe systems; Mechanisierte Ultraschallpruefung von austenitischen Rohrleitungen

    Energy Technology Data Exchange (ETDEWEB)

    Dressler, K.; Luecking, J.; Medenbach, S. [ABB ZAQ GmbH, Essen (Germany)

    1999-08-01

    The contribution explains the system of standard testing methods elaborated by ABB ZAQ GmbH for inspection of austenitic plant components. The inspection tasks explained in greater detail are basic materials testing (straight pipes, bends, and pipe specials), and inspection of welds and dissimilar welds. The techniques discussed in detail are those for detection and sizing of defects. (orig./CB) [Deutsch] Das Ziel dieses Beitrages ist die Vorstellung der von der ABB ZAQ GmbH eingesetzten Standardprueftechniken fuer die Pruefung austenitischer Anlagenkomponenten. Im einzelnen wird die Grundwerkstoffpruefung (Rohre, Boegen, Formstuecke), die Schweissnahtpruefung und die Mischnahtpruefung angesprochen. Es werden dabei die Techniken fuer `Detection` und `Sizing` differenziert betrachtet und erlaeutert. (orig.)

  13. 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

  14. Subaquatic, pressure vessels and LPG storage spheres internal inspection; Inspecao interna de esfera utilizando mergulho como acesso

    Energy Technology Data Exchange (ETDEWEB)

    Filgueira Filho, Rafael; Monteiro, Ayres [PETROBRAS, Rio de Janeiro, RJ (Brazil)

    2005-07-01

    Minimizing shut-down costs is a widespread target in the oil and gas industry. The use of new inspection techniques is one of the ways for that. This work presents a new procedure for internal inspections in pressure vessels by the non destructive testing - NDT, ACFM, using industrial diving techniques. As a pioneer experience, this method was applied in the inspection of the internal parts of the LPG sphere tank 5101 at PETROBRAS Transporte S.A. - TRANSPETRO, in Jequie's Terminal, in the state of Bahia, in december, 2003. This new method allows the reduction of indirect costs related to operational unavailability of the equipment, by the reduction of the shut-down time in approximately 50%, when compared to the demanded shut down time, when using scaffolds for accessing the internal parts. Despite of direct costs are still higher with the new methodology, this paper demonstrates the economical feasibility of this new method, based on the savings obtained with the fastest return of the equipment to operation. (author)

  15. Development of data acquisition and processing system for In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    Takama, Shinkichi; Kobayashi, Koji; Satoh, Yoshio; Koga, Yoshihiro; Shimizu, Takakazu

    1981-01-01

    In-service inspection (ISI) is required during the plant outage to assure the reliability of the components of a nuclear power plant. IHI has developed the advanced ISI system which consists of remote controlled and mechanized ultrasonic inspection devices for reactor pressure vessel examination, semi-automatic inspection instruments for piping examination with manual scan and automatic recording, data acquisition and processing system with microprocessor and mini-computer. By this system, ISI can be performed fully satisfying the requirement of ASME Code Sec. XI and minimizing operation in the high radioactive areas. All ultrasonic information is processed by the computer and the examination results such as size and location of ultrasonic indication are printed out in the form of sectional and plan view of the part examined, reproduced screen image and polar plot, etc. as well as the evaluation sheet. This system saves the elaborate work of inspection personnel and is expected to contribute to the improvement of inspection quality and to the reduction of radiation exposure of inspection personnel. (author)

  16. 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)

  17. 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)

  18. A risk-based restaurant inspection system in Los Angeles County.

    Science.gov (United States)

    Buchholz, U; Run, G; Kool, J L; Fielding, J; Mascola, L

    2002-02-01

    The majority of local health departments perform routine restaurant inspections. In Los Angeles County (LAC), California, approximately $10 million/year is spent on restaurant inspections. However, data are limited as to whether or not certain characteristics of restaurants make them more likely to be associated with foodborne incident reports. We used data from the LAC Environmental Health Management Information System (EHMIS), which records the results of all routine restaurant inspections as well as data regarding all consumer-generated foodborne incidents that led to a special restaurant inspection by a sanitarian (investigated foodborne incidents [IFBIs]). We analyzed a cohort of 10,267 restaurants inspected from 1 July 1997 to 15 November 1997. We defined a "case restaurant" as any restaurant with a routine inspection from 1 July 1997 to 15 November 1997 and a subsequent IFBI from 1 July 1997 to 30 June 1998. Noncase restaurants did not have an IFBI from I July 1997 to 30 June 1998. We looked for specific characteristics of restaurants that might be associated with the restaurant subsequently having an IFBI, including the size of restaurant (assessed by number of seats), any previous IFBIs, the overall inspection score, and a set of 38 violation codes. We identified 158 case restaurants and 10,109 noncase restaurants. In univariate analysis, middle-sized restaurants (61 to 150 seats; n = 1,681) were 2.8 times (95% confidence interval [CI] = 2.0 to 4.0) and large restaurants (>150 seats; n = 621) were 4.6 times (95% CI = 3.0 to 7.0) more likely than small restaurants (restaurants. In addition, the likelihood of a restaurant becoming a case restaurant increased as the number of IFBIs in the prior year increased (chi2 for linear trend, P value = 0.0005). Other factors significantly associated with the occurrence of an IFBI included a lower overall inspection score, the incorrect storage of food, the reuse of food, the lack of employee hand washing, the lack of

  19. International developments on implementation of Wog risk-informed inservice inspection methodology

    International Nuclear Information System (INIS)

    Balkey, K.R.; Bishop, B.A.; Canton, M.A.; Closky, N.B.; Haessler, R.L.; Kolonay, J.F.; Sharp, G.L.; Stevenson, P.R.

    2001-01-01

    The full text follows. The Westinghouse Owners Group (WOG) risk-informed inservice inspection (ISI) methodology was granted approval by the U.S. Nuclear Regulatory Commission in 1998 thereby providing an alternative to ASME Section XI Code requirements for the selection of examination locations in nuclear plant piping systems. This paper builds upon a technical paper presented at ICONE-8 that reported on the first wave of risk-informed ISI applications under development primarily focusing on those underway within the U.S. Since that time, many applications have continued within the U.S., however, much progress has been made in applying the WOG risk-informed ISI approach in several other countries. While a summary of results across the various applications will be provided, the paper will focus on the development and implementation of the WOG risk-informed ISI methodology across Europe and in Asia for both full scope and limited Class 1 scope applications. An update on future risk-informed applications, such as modifying requirements for augmented examinations for high energy line break exclusion regions and in risk-informing the safety classification of pressure boundary components in support of risk-informed regulation initiatives, will also be provided. (authors)

  20. 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.

  1. 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.

  2. Research and development on in-service inspection system for reactor vessel of FBR's

    International Nuclear Information System (INIS)

    Rindo, Hiroshi; Mitabe, Noriaki; Ara, Kuniaki; Nagai, Keiichi; Otaka, Masahiko

    1993-01-01

    In-Service Inspection (ISI) is required for main components and piping of FBRs. Visual test and volumetric examination of the reactor vessel (RV) from the outer surface are to be performed under severe conditions such as limited space, high temperature and high gamma dose rate during the reactor shutdown. Therefore, ISI should be performed by using a remote operation system, and the ISI system should be very compact. PNC has been developing the ISI system to apply to the RV inspection. Verification and performance tests of ISI system were carried out by use of the RV test model. This paper describes the system structure, system verification tests including operation and controlling the inspection robot, the functions of the visual test and the volumetric examination under the high temperature

  3. Joint optimal inspection and inventory for a k-out-of-n system

    International Nuclear Information System (INIS)

    Bjarnason, Erik T.S.; Taghipour, Sharareh; Banjevic, Dragan

    2014-01-01

    Purpose: The objective of this paper is to develop a model, which optimizes jointly the inspection frequency and the inventory level for a k-out-of-n system with repairable components whose failures are hidden. Scope: The system is periodically inspected to detect failed components, and the components are either minimally repaired or replaced with spares from the inventory. The system fails between periodic inspections if n−k+1 components are down; in that case, all failed components are inspected and rectified if possible. Otherwise, the failed components are rectified at periodic inspections. An emergency spare is ordered at a system failure, if the inventory is empty and all failed components require replacement. Methodology: Using analytical approach to find the optimal solution is computationally intensive and not practical; a simulation model is developed to solve the problem. Results: The proposed model harmonizes the maintenance and inventory policies and finds the joint optimal solution which results in a minimum total cost. Conclusion: The joint optimization model results in a lower cost compared to separate maintenance and inventory optimization models. Novelty: Few joint models for k-out-of-n systems exist, and none of them investigate repairable components whose failures are hidden and follow a non-homogeneous Poisson process. - Highlights: • We model a k-out-of-n system with hidden failures and inventory. • The system is periodically inspected and the inventory is periodically replenished. • Failed components are either replaced or minimally repaired. • A simulation model is developed to calculate the total expected cost. • The inspection interval and inventory level that minimizes the total cost is found

  4. Feasibility Study of Implementing a Mobile Collaborative Information Platform for International Safeguards Inspections

    Energy Technology Data Exchange (ETDEWEB)

    Gastelum, Zoe N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Doehle, Joel R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Toomey, Christopher M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-09-01

    In response to the growing pervasiveness of mobile technologies such as tablets and smartphones, the International Atomic Energy Agency and the U.S. Department of Energy National Laboratories have been exploring the potential use of these platforms for international safeguards activities. Specifically of interest are information systems (software, and accompanying servers and architecture) deployed on mobile devices to increase the situational awareness and productivity of an IAEA safeguards inspector in the field, while simultaneously reducing paperwork and pack weight of safeguards equipment. Exploratory development in this area has been met with skepticism regarding the ability to overcome technology deployment challenges for IAEA safeguards equipment. This report documents research conducted to identify potential challenges for the deployment of a mobile collaborative information system to the IAEA, and proposes strategies to mitigate those challenges.

  5. A delay time model for a mission-based system subject to periodic and random inspection and postponed replacement

    International Nuclear Information System (INIS)

    Yang, Li; Ma, Xiaobing; Zhai, Qingqing; Zhao, Yu

    2016-01-01

    We propose an inspection and replacement policy for a single component system that successively executes missions with random durations. The failure process of the system can be divided into two states, namely, normal and defective, following the delay time concept. Inspections are carried out periodically and immediately after the completion of each mission (random inspections). The failed state is always identified immediately, whereas the defective state can only be revealed by an inspection. If the system fails or is defective at a periodic inspection, then replacement is immediate. If, however, the system is defective at a random inspection, then replacement will be postponed if the time to the subsequent periodic inspection is shorter than a pre-determined threshold, and immediate otherwise. We derive the long run expected cost per unit time and then investigate the optimal periodic inspection interval and postponement threshold. A numerical example is presented to demonstrate the applicability of the proposed maintenance policy. - Highlights: • A delay time model of inspection is introduced for mission-based systems. • Periodic and random inspections are performed to check the state. • Replacement of the defective system at a random inspection can be postponed.

  6. [Application of laboratory information system in the management of the key indicators of quality inspection].

    Science.gov (United States)

    Guo, Ye; Chen, Qian; Wu, Wei; Cui, Wei

    2015-03-31

    To establish a system of monitoring the key indicator of quality for inspection (KIQI) on a laboratory information system (LIS), and to have a better management of KIQI. Clinical sample made in PUMCH were collected during the whole of 2014. Next, interactive input program were designed to accomplish data collecting of the disqualification rate of samples, the mistake rate of samples and the occasions of losing samples, etc. Then, a series moment of sample collection, laboratory sample arrived, sample test, sample check, response to critical value, namely, trajectory information left on LIS were recorded and the qualification rate of TAT, the notification rate of endangering result were calculated. Finally, the information about quality control were collected to build an internal quality control database and the KIQI, such as the out-of-control rate of quality control and the total error of test items were monitored. The inspection of the sample management shows the disqualification rates in 2014 were all below the target, but the rates in January and February were a little high and the rates of four wards were above 2%. The mistake rates of samples was 0.47 cases/10 000 cases, attaining the target (laboratory reports shows the qualification rates of TAT was within the acceptable range (> 95%), however the rates of blood routine in November (94.75%) was out of range. We have solved the problem by optimizing the processes. The notification rate of endangering result attained the target (≥ 98%), while the rate of timely notification is needed to improve. Quality inspection shows the CV of APTT in August (5.02%) was rising significantly, beyond the accepted CV (5.0%). We have solved the problem by changing the reagent. The CV of TT in 2014 were all below the allowable CV, thus the allowable CV of the next year lower to 10%. It is an objective and effective method to manage KIQI with the powerful management mode of database and information process capability on LIS.

  7. International Nuclear Information System (INIS)

    International Nuclear Information System (INIS)

    1987-01-01

    Depicts the nature and operations of the first truly international, decentralized and computerized information processing and dissemination system, INIS. The products of the system, consisting of various literature indexes issued in both printed form and on magnetic tapes are described and their utility to scientists is demonstrated

  8. A Feasibility Study on the Inspection System Development of Underground Cavities Using Neutron Source

    International Nuclear Information System (INIS)

    Yim, Che Wook; Kim, Song Hyun; Kim, Do Hyun; Shin, Chang Ho

    2015-01-01

    The detection efficiency using the gravimetry method is significantly low; therefore, it requires large surveying time. The magnetometry method detects the cavities by the magnitude of the magnetic field. However, the magnetometry method is problematical in urban areas due to pipes and electrical installations. GPR is the method that uses high frequency electromagnetic wave. This method is widely used for the inspection; however, the detection accuracy of sinkholes can be low in specific soil types. In this study, to verify the feasibility of the neutron source-based inspection system to detect the cavity detection, the Monte Carlo simulation was performed using neutron source. The analysis shows that the detection of the cavity with the given condition is possible when the diameter of cavity is over 100 cm. However, the detection efficiency can be enough increased if some optimization strategies for the inspection are developed. Also, it is expected that the proposed inspection method can detect the expected locations of the cavities

  9. A Feasibility Study on the Inspection System Development of Underground Cavities Using Neutron Source

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Che Wook; Kim, Song Hyun; Kim, Do Hyun; Shin, Chang Ho [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    The detection efficiency using the gravimetry method is significantly low; therefore, it requires large surveying time. The magnetometry method detects the cavities by the magnitude of the magnetic field. However, the magnetometry method is problematical in urban areas due to pipes and electrical installations. GPR is the method that uses high frequency electromagnetic wave. This method is widely used for the inspection; however, the detection accuracy of sinkholes can be low in specific soil types. In this study, to verify the feasibility of the neutron source-based inspection system to detect the cavity detection, the Monte Carlo simulation was performed using neutron source. The analysis shows that the detection of the cavity with the given condition is possible when the diameter of cavity is over 100 cm. However, the detection efficiency can be enough increased if some optimization strategies for the inspection are developed. Also, it is expected that the proposed inspection method can detect the expected locations of the cavities.

  10. Human error considerations and annunciator effects in determining optimal test intervals for periodically inspected standby systems

    International Nuclear Information System (INIS)

    McWilliams, T.P.; Martz, H.F.

    1981-01-01

    This paper incorporates the effects of four types of human error in a model for determining the optimal time between periodic inspections which maximizes the steady state availability for standby safety systems. Such safety systems are characteristic of nuclear power plant operations. The system is modeled by means of an infinite state-space Markov chain. Purpose of the paper is to demonstrate techniques for computing steady-state availability A and the optimal periodic inspection interval tau* for the system. The model can be used to investigate the effects of human error probabilities on optimal availability, study the benefits of annunciating the standby-system, and to determine optimal inspection intervals. Several examples which are representative of nuclear power plant applications are presented

  11. Image formation simulation for computer-aided inspection planning of machine vision systems

    Science.gov (United States)

    Irgenfried, Stephan; Bergmann, Stephan; Mohammadikaji, Mahsa; Beyerer, Jürgen; Dachsbacher, Carsten; Wörn, Heinz

    2017-06-01

    In this work, a simulation toolset for Computer Aided Inspection Planning (CAIP) of systems for automated optical inspection (AOI) is presented along with a versatile two-robot-setup for verification of simulation and system planning results. The toolset helps to narrow down the large design space of optical inspection systems in interaction with a system expert. The image formation taking place in optical inspection systems is simulated using GPU-based real time graphics and high quality off-line-rendering. The simulation pipeline allows a stepwise optimization of the system, from fast evaluation of surface patch visibility based on real time graphics up to evaluation of image processing results based on off-line global illumination calculation. A focus of this work is on the dependency of simulation quality on measuring, modeling and parameterizing the optical surface properties of the object to be inspected. The applicability to real world problems is demonstrated by taking the example of planning a 3D laser scanner application. Qualitative and quantitative comparison results of synthetic and real images are presented.

  12. Development and validation of real-time SAFT-UT system for inservice inspection of LWRs

    International Nuclear Information System (INIS)

    Doctor, S.R.; Hall, T.E.; Reid, L.D.; Mart, G.A.

    1988-01-01

    The Pacific Northwest Laboratory is working to design, fabricate, and evaluate a real-time flaw detection and characterization system based on the synthetic aperture focusing technique for ultrasonic testing (SAFT-UT). The system is designed to perform inservice inspection of light-water reactor components. Included objectives of this program for the Nuclear Regulatory Commission are to develop procedures for system calibration and field operation, to validate the system through laboratory and field inspections, and to generate an engineering database to support ASME Code acceptance of the technology. This progress report covers the programmatic work from October 1986 through September 1987. (author)

  13. Robotic system for remote inspection of underground storage tanks

    International Nuclear Information System (INIS)

    Griebenow, B.L.; Martinson, L.M.

    1990-01-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO), operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE). WINCO's mission is to process government owned spent nuclear fuel. The process involves dissolving the fuel and extracting off uranium. The waste from this process is temporarily stored at the ICPP in underground storage tanks. The tanks were put in service between 1953 and 1966 and are operating 10 to 15 years beyond their design life. Five of the tanks will be replaced by 1998. The integrity of the remaining six tanks must be verified to continue their use until they can be replaced at a later data. In order to verify the tank integrity, a complete corrosion analysis must be performed. This analysis will require a remote visual inspection of the tank surfaces

  14. Strategy of Risk-Informed Inspection for Secondary Systems in NPPs

    International Nuclear Information System (INIS)

    Kim, So Young; Heo, Gyun Young

    2012-01-01

    Recently, unexpected accidents such as large-scale blackout have been occurred due to increasing demand of electricity. The unplanned trips have great influence over the economics although they rarely affect the safety of system. Because the cost for inspection and maintenance is limited, it is beneficial not only economically to take follow-up action in a timely manner to prevent plant trip but also in safety by protecting against the risk which is occurred from trip. In nuclear power plants (NPPs), the importance about risk-informed service such as inspection, maintenance and replacement is becoming on the rise. Risk-informed techniques such as in-service test, in-service inspection, design guide change and etc. are already used in nuclear field but these techniques are applied focusing on primary system for safety-related regulatory issues. It is needed to consider the optimization of inspection informed risk for entire plant including secondary system which is not applied enough. The study about risk-based inspection for boilers in thermal power field is in progress actively, but not for turbine cycle, which is similar with nuclear industry. Today, the most of inspections or tests for turbine cycle are time-based maintenance, being performed on time. It is required to perform condition-based maintenance by evaluating risk analyzing both of probability and consequence simultaneously about damage mechanisms that can be predicted by equipment or devices configuring the secondary system. Probability of failure (POF) is analyzed in terms of materials' ageing mechanisms, but consequence of failure (COF) should be evaluated in terms of thermohydraulic condition then it is needed to check power loss and period of maintenance. This paper is going to propose the idea to quantify the consequence of failure using the fault tree and simulation for secondary system, and propose quantitative risk-informed inspection by these approaches

  15. High throughput web inspection system using time-stretch real-time imaging

    Science.gov (United States)

    Kim, Chanju

    Photonic time-stretch is a novel technology that enables capturing of fast, rare and non-repetitive events. Therefore, it operates in real-time with ability to record over long period of time while having fine temporal resolution. The powerful property of photonic time-stretch has already been employed in various fields of application such as analog-to-digital conversion, spectroscopy, laser scanner and microscopy. Further expanding the scope, we fully exploit the time-stretch technology to demonstrate a high throughput web inspection system. Web inspection, namely surface inspection is a nondestructive evaluation method which is crucial for semiconductor wafer and thin film production. We successfully report a dark-field web inspection system with line scan speed of 90.9 MHz which is up to 1000 times faster than conventional inspection instruments. The manufacturing of high quality semiconductor wafer and thin film may directly benefit from this technology as it can easily locate defects with area of less than 10 microm x 10 microm where it allows maximum web flow speed of 1.8 km/s. The thesis provides an overview of our web inspection technique, followed by description of the photonic time-stretch technique which is the keystone in our system. A detailed explanation of each component is covered to provide quantitative understanding of the system. Finally, imaging results from a hard-disk sample and flexible films are presented along with performance analysis of the system. This project was the first application of time-stretch to industrial inspection, and was conducted under financial support and with close involvement by Hitachi, Ltd.

  16. 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.

  17. An international survey of in-service inspection experience with prestressed concrete pressure vessels and containments for nuclear reactors

    International Nuclear Information System (INIS)

    1982-04-01

    An international survey is presented of experience obtained from the in-service surveillance of prestressed concrete pressure vessels and containments for nuclear reactors. Some information on other prestressed concrete structures is also given. Experience has been gained during the working life of such structures in Western Europe and the USA over the years since 1967. For each country a summary is given of the nuclear programme, national standards and Codes of Practice, and the detailed in-service inspection programme. Reports are then given of the actual experience obtained from the inspection programme and the methods of measurement, examination and reporting employed in each country. A comprehensive bibliography of over 100 references is included. The appendices contain information on nuclear power stations which are operating, under construction or planned worldwide and which employ either prestressed concrete pressure vessels or containments. (U.K.)

  18. Risk-based Inspection Guide for the Susquehanna Station HPCI system

    International Nuclear Information System (INIS)

    Travis, R.; Higgins, J.; Gunther, W.; Shier, W.

    1992-11-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A system Risk-based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Susquehanna Steam Electric Station (SSES) which is operated by Pennsylvania Power ampersand Light (PP ampersand L). Included in this S-RIG is a discussion of the role of HPCI in mitigating accidents and a presentation of PRA-based failure modes which could prevent proper operation of the system. The S-RIG uses industry operating experience, including plant-specific illustrative examples, to augment the basic PRA failure modes. It is designed to be used as a reference for both routine inspections and the evaluation of the significance of component failures

  19. NRC Information No. 91-29: Deficiencies identified during electrical distribution system functional inspections

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    During multidisciplinary inspections, the US Nuclear Regulatory Commission (NRC) has identified many deficiencies related to the electrical distribution system. To address these deficiencies, the NRC has developed an inspection to specifically evaluate the electrical distribution system. During the last year, the NRC completed eight EDSFIs, performing at least one in each of the several common deficiencies in the licensees' programs and in the electrical distribution systems as designed and configured at each plant. These deficiencies included inadequate ac voltages at the 480 Vac and 120 Vac distribution levels, inadequate procedures to test circuit breakers, and inadequate determinations and evaluations of setpoints

  20. Evaluation of Contamination Inspection and Analysis Methods through Modeling System Performance

    Science.gov (United States)

    Seasly, Elaine; Dever, Jason; Stuban, Steven M. F.

    2016-01-01

    Contamination is usually identified as a risk on the risk register for sensitive space systems hardware. Despite detailed, time-consuming, and costly contamination control efforts during assembly, integration, and test of space systems, contaminants are still found during visual inspections of hardware. Improved methods are needed to gather information during systems integration to catch potential contamination issues earlier and manage contamination risks better. This research explores evaluation of contamination inspection and analysis methods to determine optical system sensitivity to minimum detectable molecular contamination levels based on IEST-STD-CC1246E non-volatile residue (NVR) cleanliness levels. Potential future degradation of the system is modeled given chosen modules representative of optical elements in an optical system, minimum detectable molecular contamination levels for a chosen inspection and analysis method, and determining the effect of contamination on the system. By modeling system performance based on when molecular contamination is detected during systems integration and at what cleanliness level, the decision maker can perform trades amongst different inspection and analysis methods and determine if a planned method is adequate to meet system requirements and manage contamination risk.

  1. Inspection logistics planning for multi-stage production systems with applications to semiconductor fabrication lines

    Science.gov (United States)

    Chen, Kyle Dakai

    Since the market for semiconductor products has become more lucrative and competitive, research into improving yields for semiconductor fabrication lines has lately received a tremendous amount of attention. One of the most critical tasks in achieving such yield improvements is to plan the in-line inspection sampling efficiently so that any potential yield problems can be detected early and eliminated quickly. We formulate a multi-stage inspection planning model based on configurations in actual semiconductor fabrication lines, specifically taking into account both the capacity constraint and the congestion effects at the inspection station. We propose a new mixed First-Come-First-Serve (FCFS) and Last-Come-First-Serve (LCFS) discipline for serving the inspection samples to expedite the detection of potential yield problems. Employing this mixed FCFS and LCFS discipline, we derive approximate expressions for the queueing delays in yield problem detection time and develop near-optimal algorithms to obtain the inspection logistics planning policies. We also investigate the queueing performance with this mixed type of service discipline under different assumptions and configurations. In addition, we conduct numerical tests and generate managerial insights based on input data from actual semiconductor fabrication lines. To the best of our knowledge, this research is novel in developing, for the first time in the literature, near-optimal results for inspection logistics planning in multi-stage production systems with congestion effects explicitly considered.

  2. Inspection system of radioactive contamination in foods and its results in Yokohama City

    International Nuclear Information System (INIS)

    Morita, Masahiro

    1993-01-01

    Accompanying the Chernobyl nuclear power plant accident occurred on April 26, 1986, the radioactive contamination of the foods imported from Europe became problems. Consequently, the Ministry of Health and Welfare stipulated the temporary limit of radioactive concentration in imported foods in terms of the total of Cs-134 and Cs-137 at less than 370 becquerel per 1 kg of foods in November, 1986, and the inspection system was tightened. In Yokohama, in view of securing the safety of foods and eliminating the anxiety of citizen, the measuring instruments for radioactivity were installed in the Hygiene Laboratory in 1986 and in the Food Hygiene Inspection Stations in Central Wholesale Market in 1987, and the inspection was begun. So far 720 subjects were inspected, but there was none that exceeds the temporary limit. The period and the method of executing the inspection and the results of nuclide analysis, screening inspection and so on are reported. It was judged that at the present point of time, there is not much influence to the life of citizen. (K.I.)

  3. Verification tests for remote controlled inspection system in nuclear power plants

    International Nuclear Information System (INIS)

    Kohno, Tadaaki

    1986-01-01

    Following the increase of nuclear power plants, the total radiation exposure dose accompanying inspection and maintenance works tended to increase. Japan Power Engineering and Inspection Corp. carried out the verification test of a practical power reactor automatic inspection system from November, 1981, to March, 1986, and in this report, the state of having carried out this verification test is described. The objects of the verification test were the equipment which is urgently required for reducing radiation exposure dose, the possibility of realization of which is high, and which is important for ensuring the safety and reliability of plants, that is, an automatic ultrasonic flaw detector for the welded parts of bend pipes, an automatic disassembling and inspection system for control rod driving mechanism, a fuel automatic inspection system, and automatic decontaminating equipments for steam generator water chambers, primary system crud and radioactive gas in coolant. The results of the verification test of these equipments were judged as satisfactory, therefore, the application to actual plants is possible. (Kako, I.)

  4. Development of in-service inspection system for core support graphite structures in the high temperature engineering test reactor (HTTR)

    Energy Technology Data Exchange (ETDEWEB)

    Sumita, Junya; Hanawa, Satoshi; Kikuchi, Takayuki; Ishihara, Masahiro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2003-03-01

    Visual inspection of core support graphite structures using TV camera as in-service inspection and measurement of material characteristics using surveillance test specimens are planned in the High Temperature Engineering Test Reactor (HTTR) to confirm structural integrity of the core support graphite structures. For the visual inspection, in-service inspection system developed from September 1996 to June 1998, and pre-service inspection using the system was carried out. As the result of the pre-service inspection, it was validated that high quality of visual inspection with TV camera can be carried out, and also structural integrity of the core support graphite structures at the initial stage of the HTTR operation was confirmed. (author)

  5. Validation Test Results for Orthogonal Probe Eddy Current Thruster Inspection System

    Science.gov (United States)

    Wincheski, Russell A.

    2007-01-01

    Recent nondestructive evaluation efforts within NASA have focused on an inspection system for the detection of intergranular cracking originating in the relief radius of Primary Reaction Control System (PCRS) Thrusters. Of particular concern is deep cracking in this area which could lead to combustion leakage in the event of through wall cracking from the relief radius into an acoustic cavity of the combustion chamber. In order to reliably detect such defects while ensuring minimal false positives during inspection, the Orthogonal Probe Eddy Current (OPEC) system has been developed and an extensive validation study performed. This report describes the validation procedure, sample set, and inspection results as well as comparing validation flaws with the response from naturally occuring damage.

  6. Development of planar CT system for multi-layer PCB inspection

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Youn, Hanbean; Kam, Soohwa; Park, Eunpyeong; Kim, Ho Kyung [Pusan National University, Busan (Korea, Republic of)

    2015-05-15

    X-ray defect inspection apparatus can be used in the production line to inspect the PCB. However, a simple X-ray radiography cannot discriminate defects from the multi-layer PCBs because the layers of them overlays the defects. To complement this issue, computed tomography (CT) technology is applied to the NDT system which can offer 3-dimensional information of object. However, CT requires hundreds of projection images to examine a single PCB, hence real-time inspection is nearly impossible. In this study, we develop a planar computed tomography (pCT) system appropriate for the multi-layer PCB inspection. For the image reconstruction of planar cross-section images, we use the digital tomosynthesis (DTS) concept in association with the limited angle scanning. and performance characterization of the pCT system for the PCB inspection. The 3-d Fourier characteristics and more quantitative performance, such as contrast, uniformity, depth resolution will be presented. The cross-sectional images of multi-layer PCBs will also be demonstrated.

  7. INIS - International Nuclear Information System

    International Nuclear Information System (INIS)

    1995-01-01

    The paper presents International Nuclear Information System (INIS): history of its development; INIS support products (INIS Reference Series, Friendly Inputting of Bibliographic Records software); INIS output products (INIS Atomindex, magnetic tapes, online service, database on CD-ROM, microfiche service); INIS philosophy; input of INIS database by subject areas; and examples of INIS input

  8. International Instructional Systems: Social Studies

    Science.gov (United States)

    Brant, Jacek; Chapman, Arthur; Isaacs, Tina

    2016-01-01

    This paper reports on research conducted as part of the International Instructional System Study that explored five subject areas across nine jurisdictions in six high-performing countries. The Study's overall aim was to understand what, if anything, there is in common in the curricula and assessment arrangements among the high-performing…

  9. Analysis and optimization on in-vessel inspection robotic system for EAST

    International Nuclear Information System (INIS)

    Zhang, Weijun; Zhou, Zeyu; Yuan, Jianjun; Du, Liang; Mao, Ziming

    2015-01-01

    Since China has successfully built her first Experimental Advanced Superconducting TOKAMAK (EAST) several years ago, great interest and demand have been increasing in robotic in-vessel inspection/operation systems, by which an observation of in-vessel physical phenomenon, collection of visual information, 3D mapping and localization, even maintenance are to be possible. However, it has been raising many challenges to implement a practical and robust robotic system, due to a lot of complex constraints and expectations, e.g., high remanent working temperature (100 °C) and vacuum (10"−"3 pa) environment even in the rest interval between plasma discharge experiments, close-up and precise inspection, operation efficiency, besides a general kinematic requirement of D shape irregular vessel. In this paper we propose an upgraded robotic system with redundant degrees of freedom (DOF) manipulator combined with a binocular vision system at the tip and a virtual reality system. A comprehensive comparison and discussion are given on the necessity and main function of the binocular vision system, path planning for inspection, fast localization, inspection efficiency and success rate in time, optimization of kinematic configuration, and the possibility of underactuated mechanism. A detailed design, implementation, and experiments of the binocular vision system together with the recent development progress of the whole robotic system are reported in the later part of the paper, while, future work and expectation are described in the end.

  10. The data correction algorithms in sup 6 sup 0 Co train inspection system

    CERN Document Server

    Yuan Ya Ding; LiuXiMing; Miao Ji Cheng

    2002-01-01

    Because of the physical characteristics of the sup 6 sup 0 Co train inspection system and the application of high-speed data collection system based on current integral, the original images have been distorted in a certain degree. Authors investigate into the reasons why the distortion comes into being, and accordingly present the data correction algorithm

  11. Analysis and optimization on in-vessel inspection robotic system for EAST

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Weijun, E-mail: zhangweijun@sjtu.edu.cn; Zhou, Zeyu; Yuan, Jianjun; Du, Liang; Mao, Ziming

    2015-12-15

    Since China has successfully built her first Experimental Advanced Superconducting TOKAMAK (EAST) several years ago, great interest and demand have been increasing in robotic in-vessel inspection/operation systems, by which an observation of in-vessel physical phenomenon, collection of visual information, 3D mapping and localization, even maintenance are to be possible. However, it has been raising many challenges to implement a practical and robust robotic system, due to a lot of complex constraints and expectations, e.g., high remanent working temperature (100 °C) and vacuum (10{sup −3} pa) environment even in the rest interval between plasma discharge experiments, close-up and precise inspection, operation efficiency, besides a general kinematic requirement of D shape irregular vessel. In this paper we propose an upgraded robotic system with redundant degrees of freedom (DOF) manipulator combined with a binocular vision system at the tip and a virtual reality system. A comprehensive comparison and discussion are given on the necessity and main function of the binocular vision system, path planning for inspection, fast localization, inspection efficiency and success rate in time, optimization of kinematic configuration, and the possibility of underactuated mechanism. A detailed design, implementation, and experiments of the binocular vision system together with the recent development progress of the whole robotic system are reported in the later part of the paper, while, future work and expectation are described in the end.

  12. Mobile robot teleoperation system for plant inspection based on collecting and utilizing environment data

    International Nuclear Information System (INIS)

    Kawabata, Kuniaki; Watanabe, Nobuyasu; Asama, Hajime; Kita, Nobuyuki; Yang, Hai-quan

    2004-01-01

    This paper describes about development of a mobile robot teleoperation system for plant inspection. In our system, the robot is an agent for collecting the environment data and is also teleoperated by the operator utilizing such accumulated environment data which is displayed on the operation interface. The robot equips many sensors for detecting the state of the robot and the environment. Such redundant sensory system can be also utilized to collect the working environment data on-site while the robot is patrolling. Here, proposed system introduces the framework of collecting and utilizing environment data for adaptive plant inspection using the teleoperated robot. A view simulator is primarily aiming to facilitate evaluation of the visual sensors and algorithms and is also extended as the Environment Server, which is the core technology of the digital maintenance field for the plant inspection. In order to construct detailed seamless digital maintenance field mobile robotic technology is utilized to supply environment data to the server. The sensory system on the robot collect the environment data on-site and such collected data is uploaded to the Environment Server for compiling accurate digital environment data base. The robot operator also can utilize accumulated environment data by referring to the Environment Server. In this paper, we explain the concept of our teleoperation system based on collecting and utilizing environment data. Using developed system, inspection patrol experiments were attempted in the plant mock-up. Experimental results are shown by using an omnidirectional mobile robot with sensory system and the Environment Server. (author)

  13. Development of a Fibre-Phased Array Laser-EMAT Ultrasonic System for Defect Inspection

    International Nuclear Information System (INIS)

    Pei, C; Demachi, K; Koyama, K; Uesaka, M; Fukuchi, T; Chen, Z

    2014-01-01

    In this work, a phased array laser ultrasound system with using fibre optic delivery and a custom-designed focusing objective lens has been developed for enhancing the ultrasound generation. The fibre-phased array method is applied to improve the sensitivity and detecting ability of the laser-EMAT system for defect inspection

  14. Application and study of advanced network technology in large container inspection system

    International Nuclear Information System (INIS)

    Li Zheng; Kang Kejun; Gao Wenhuan; Wang Jingjin

    1996-01-01

    Large Container Inspection System (LCIS) based on radiation imaging technology is a powerful tool for the customs to check the contents inside a large container without opening it. An image distributed network system is composed of center manager station, image acquisition station, environment control station, inspection processing station, check-in station, check-out station, database station by using advanced network technology. Mass data, such as container image data, container general information, manifest scanning data, commands and status, must be on-line transferred between different stations. Advanced network technology and software programming technique are presented

  15. MRP-227 Reactor vessel internals inspection planning and initial results at the Oconee nuclear station unit 2

    International Nuclear Information System (INIS)

    Davidsaver, S.B.; Fyfitch, S.; Whitaker, D.E.; Doss, R.L.

    2015-01-01

    The U.S. PWR industry has pro-actively developed generic inspection requirements and standards for reactor vessel (RV) internals. The Electric Power Research Institute (EPRI) Pressurized Water Reactor (PWR) Materials Reliability Program (MRP) has issued MRP-227-A and MRP-228 with mandatory and needed requirements based on the Nuclear Energy Institute (NEI) document NEI 03-08. The inspection and evaluation guidelines contained in MRP-227-A consider eight age-related degradation mechanisms: stress corrosion cracking (SCC), irradiation-assisted stress corrosion cracking (IASCC), wear, fatigue, thermal aging embrittlement, irradiation embrittlement, void swelling and irradiation growth, and thermal and irradiation-enhanced stress relaxation or irradiation-enhanced creep. This paper will discuss the decision planning efforts required for implementing the MRP-227-A and MRP-228 requirements and the results of these initial inspections at the Oconee Nuclear power station (ONS) units. Duke Energy and AREVA overcame a significant technology and NDE challenge by successfully completing the first-of-a-kind MRP-227-A scope requirements at ONS-1 in one outage below the estimated dose and with zero safety issues or events. This performance was repeated at ONS-2 a year later. The remote NDE tooling and processes developed to examine the MRP-227-A scope for ONS-1 and ONS-2 are transferable to other PWRs

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

    Directory of Open Access Journals (Sweden)

    Deok-Seok Seo

    2015-01-01

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

  17. Changes in security systems and manufacture equipment and inspection

    International Nuclear Information System (INIS)

    Paloma, J. J.; Moraga, J. L.

    2015-01-01

    From the beginning of its industrial activity 30 years ago, the Juzbado factory of Enusa Group has maintained a strong commitment to safety and technological innovation. As a result, we have development new equipment and constantly improving the existing ones, as well as the facilities of the factory in accordance with the internal procedures, with multidisciplinary design teams and review teams. (Author)

  18. Buyer Liability and Voluntary Inspections in International Greenhouse Gas Emissions Trading. A Laboratory Study

    International Nuclear Information System (INIS)

    Cason, T.N.

    2003-01-01

    This paper reports a preliminary laboratory experiment in which traders make investments to increase the reliability of tradable instruments that represent greenhouse gas emissions allowances. In one half of the sessions these investments are unobservable, while in the other half traders can invite costless and accurate inspections that make reliability investments public. We implement a buyer liability rule, so that if emissions reductions are unreliable (i.e., sellers default), the buyer of the allowances cannot redeem them to cover emissions. We find that allowing inspections significantly increases the reliability investment rate and overall efficiency. Prices of uninspected allowances usually trade at a substantial discount due to the buyer liability rule, which provides a strong market incentive for sellers to invest in reliability

  19. Mobile CT-System for In-situ Inspection in the LHC at CERN

    CERN Document Server

    Sauerwein, C; Caspers, F; Dalin, J M; Haemmerle, V; Tiseanu, I; Tock, J P

    2010-01-01

    For the inspection of certain critical elements of the LHC machine a mobile computed tomography system has been developed and built. This instrument has to satisfy stringent space, volume and weight requirements in order to be transportable and usable to any interconnection location in the LHC tunnel. Particular regions of interest in the interconnection zones between adjacent magnets are the plug in modules (PIM), the soldered splices in the superconducting bus-bars and the interior of the quench diode container. This system permits detailed inspection of these regions without needing to break the insulation vacuum. Limited access for the x-ray tube and the detector required the development of a special type of partial tomography, together with suitable reconstruction techniques for 3 D volume generation from radiographic projections. The layout of the complete machine, the limited angle tomography, as well as a number of radiographic and tomographic inspection results is presented.

  20. 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)

  1. International cooperation program on non-destructive inspection. Overview of PINC and PARENT

    International Nuclear Information System (INIS)

    Komura, Ichiro

    2016-01-01

    PINC (The Program for the Inspection of Nickel Alloy Components) and its successor program PARENT (The Program to Assess the Reliability of Emerging Nondestructive Techniques) are the programs on the verification of nondestructive inspection technology for detecting / dimension-evaluating the stress corrosion cracking (SCC) generated in the weld zone of nickel-based alloy. The US Nuclear Regulatory Commission plays a leading role, and the institutions of the United States, Japan, Korea, Sweden, Finland, and Switzerland participate in them. PINC was run from 2003 to 2009, and PARENT is currently underway with a schedule from 2010 to July 2017, including the extension period after July 2015. This paper outlined the implementation items and test results / achievements of PINC and PARENT programs. The target parts of PINC were a safe-end reducer and a reactor bottom instrument tube rest, and the flaw detection test and its analytical evaluation were carried out with a focus on the detectability and the sizing accuracy of defects. As a feature of the verification test of the non-destructive inspection technology in PARENT, two kinds of flaw detection tests, namely blind test and open test, are distinctively carried out. (A.O.)

  2. Development of optical inspection system of L-band SRF cavity

    International Nuclear Information System (INIS)

    Tajima, Yujiro; Iwashita, Yoshihisa; Hayano, Hitoshi

    2008-01-01

    The International Linear Collider (ILC) will require about 15,000 1.3 GHz superconducting radio frequency (SRF) accelerating cavities with high accelerating gradient (>35 MV/m) in its main linac. The high yield (80%) of successful high gradient cavities is necessary. Both of the yield and the accelerating gradient of SRF cavities does not reach the required level at present. We think that the gradient of the SRF cavities is limited by irregularities on the interior surface of the cavities, for example, fine dusts (1μm), balls (100μm) and pits (100μm): electrons emitted from the fine dusts by the tunnel effect are accelerated in the electric field, and consume the stored energy of the cavities (Field Emission). The balls and pits cause a breakdown by a magnetic field enhancement or a thermal current concentration (Thermal Breakdown). To prevent these problems the interior surface are treated by polishing and rinsing. The relation between the surface states and the gradient limitations, however, is still not clarified. To study the relation, we are developing an optical inspection system of the interior surface. (author)

  3. Research on image reconstruction of DR/SSCT security inspection system

    International Nuclear Information System (INIS)

    Li Jian; Cong Peng

    2008-01-01

    On the basis of DR (Digital Radiography)/CT security inspection system, DR/SSCT (single slice spiral CT) security inspection system was developed. This spiral CT system can improve the CT system's drawbacks. The research work includes in replacing the former data acquisition system by a new system which can acquire projection data of multi-slices and devising the SSCT reconstruction algorithms. Simulation experiments and practical experiments were devised to contrast several algorithms. Interpolation technique was operated in detectors data in order to improve the algorithms. In conclusion, the system exploits an algorithm of weighted average of 360 degree LI (Linear Interpolation) and JH-HI (Jiang Hsieh-Half scan Interpolation). (authors)

  4. Laser Shearography Inspection of TPS (Thermal Protection System) Cork on RSRM (Reusable Solid Rocket Motors)

    Science.gov (United States)

    Lingbloom, Mike; Plaia, Jim; Newman, John

    2006-01-01

    Laser Shearography is a viable inspection method for detection of de-bonds and voids within the external TPS (thermal protection system) on to the Space Shuttle RSRM (reusable solid rocket motors). Cork samples with thicknesses up to 1 inch were tested at the LTI (Laser Technology Incorporated) laboratory using vacuum-applied stress in a vacuum chamber. The testing proved that the technology could detect cork to steel un-bonds using vacuum stress techniques in the laboratory environment. The next logical step was to inspect the TPS on a RSRM. Although detailed post flight inspection has confirmed that ATK Thiokol's cork bonding technique provides a reliable cork to case bond, due to the Space Shuttle Columbia incident there is a great interest in verifying bond-lines on the external TPS. This interest provided and opportunity to inspect a RSRM motor with Laser Shearography. This paper will describe the laboratory testing and RSRM testing that has been performed to date. Descriptions of the test equipment setup and techniques for data collection and detailed results will be given. The data from the test show that Laser Shearography is an effective technology and readily adaptable to inspect a RSRM.

  5. Container code recognition in information auto collection system of container inspection

    International Nuclear Information System (INIS)

    Su Jianping; Chen Zhiqiang; Zhang Li; Gao Wenhuan; Kang Kejun

    2003-01-01

    Now custom needs electrical application and automatic detection. Container inspection should not only give the image of the goods, but also auto-attain container's code and weight. Its function and track control, information transfer make up the Information Auto Collection system of Container Inspection. Code Recognition is the point. The article is based on model match, the close property of character, and uses it to recognize. Base on checkout rule, design the adjustment arithmetic, form the whole recognition strategy. This strategy can achieve high recognition ratio and robust property

  6. Gamma signatures of the C-BORD Tagged Neutron Inspection System

    Directory of Open Access Journals (Sweden)

    Sardet A.

    2018-01-01

    Full Text Available In the frame of C-BORD project (H2020 program of the EU, a Rapidly relocatable Tagged Neutron Inspection System (RRTNIS is being developed to non-intrusively detect explosives, chemical threats, and other illicit goods in cargo containers. Material identification is performed through gamma spectroscopy, using twenty NaI detectors and four LaBr3 detectors, to determine the different elements composing the inspected item from their specific gamma signatures induced by fast neutrons. This is performed using an unfolding algorithm to decompose the energy spectrum of a suspect item, selected by X-ray radiography and on which the RRTNIS inspection is focused, on a database of pure element gamma signatures. This paper reports on simulated signatures for the NaI and LaBr3 detectors, constructed using the MCNP6 code. First experimental spectra of a few elements of interest are also presented.

  7. Use of artificial intelligence techniques for visual inspection systems prototyping. Application to magnetoscopy

    International Nuclear Information System (INIS)

    Pallas, Christophe

    1987-01-01

    The automation of visual inspection is a complex task that requires collaboration between experts, for example inspection specialist, vision specialist. on-line operators. Solving such problems through prototyping promotes this collaboration: the use of a non specific programming environment allows rapid, concrete checking of method validity, thus leading incrementally to the final system. In this context, artificial intelligence techniques permit easy, extensible, and modular design of the prototype, together with heuristic solution building. We define and achieve the SPOR prototyping environment, based on object-oriented programming and rules-basis managing. The feasibility and the validity of an heuristic method for automated visual inspection in fluoroscopy have been proved through prototyping in SPOR. (author) [fr

  8. Preliminary inspection of secondary cooling system piping for maintenance plan in JMTR

    International Nuclear Information System (INIS)

    Hanakawa, Hiroki; Hanawa, Yoshio; Izumo, Hironobu; Fukasaku, Akitomi; Nagao, Yoshiharu; Miyazawa, Masataka; Niimi, Motoji

    2008-01-01

    The JMTR is under the refurbishment and will start on FY 2011. The JMTR will operate for about 20 years from 2011. Before this JMTR operation, preliminary inspection of secondary cooling system piping was carried out in order to make a maintenance plan. As the results of this inspection, it was confirmed that the corrosion was reached by piping ingot, or decrease of piping thickness could hardly be observed. Therefore, it was confirmed that the strength or the functionality of the piping had been maintained by usual operation and maintenance. According to the results of this inspection, the basic date for maintenances are confirmed and it is clear to be able to make the maintenances plan in future. (author)

  9. 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

  10. Design and implementation of check out station for large container inspection system

    International Nuclear Information System (INIS)

    Yao Dongsheng; Gao Wenhuan; Kang Kejun

    1997-01-01

    In Large Container Inspection System (LCIS), Check Out Station (COS) is in charge of deciding whether a container is allowed to pass or has to be opened for checking. Several different top level architecture designs for COS are discussed and analyzed according to the practical requirements of COS

  11. The research on rectification and amplification of the image in mobile large container inspection system

    International Nuclear Information System (INIS)

    Jin Hui; Cheng Jianping; Chen Zhiqiang; Zhang Li

    2001-01-01

    The author introduces a geometrical rectification algorithm of the image in mobile large container inspection system. The comparison and discussion of the image before and after the rectification have been given. Amplification algorithms of the images are discussed. With all the algorithms, the quality of the images has been improved

  12. Electrical and electronic subsystems of a nuclear waste tank annulus inspection system

    International Nuclear Information System (INIS)

    Evenson, R.J.

    1981-06-01

    The nuclear waste tank annulus inspection system is designed specifically for use at the Nuclear Regulatory Commission's Nuclear Fuel Services Facility at West Valley, New York. This system sends a television and photographic camera into the space between the walls of a double-shell nuclear waste tank to obtain images of the inner and outer walls at precisely known locations. The system is capable of inspecting a wall section 14 ft wide by 27 ft high. Due to the high temperature and radiation of the annulus environment, the operating life for the inspection device is uncertain, but is expected to be at least 100 h, with 1000 R/h at 82 0 C. The film camera is shielded with 1/2 in. of lead to minimize radiation fogging of the film during a 25-min picture taking excursion. The operation of the inspection system is semiautomated with remote manual prepositioning of the camera, followed by a computer controlled wall scan. This apparatus is currently set up to take an array of contiguous pictures, but is adaptable to other modes of operation

  13. Thresholding using two-dimensional histogram and watershed algorithm in the luggage inspection system

    International Nuclear Information System (INIS)

    Chen Jingyun; Cong Peng; Song Qi

    2006-01-01

    The authors present a new DR image segmentation method based on two-dimensional histogram and watershed algorithm. The authors use watershed algorithm to locate threshold on the vertical projection plane of two-dimensional histogram. This method is applied to the segmentation of DR images produced by luggage inspection system with DR-CT. The advantage of this method is also analyzed. (authors)

  14. 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.

  15. Completion of development of robotics systems for inspecting unpiggable transmission pipelines.

    Science.gov (United States)

    2013-02-01

    This document presents the final report for a program focusing on the completion of the : research, development and demonstration effort, which was initiated in 2001, for the : development of two robotic systems for the in-line, live inspection of un...

  16. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

    Energy Technology Data Exchange (ETDEWEB)

    Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

    1994-08-01

    The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors.

  17. Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection

    International Nuclear Information System (INIS)

    Vo, T.V.; Smith, B.W.; Simonen, F.A.; Gore, B.F.

    1994-08-01

    The goals of the Evaluation and Improvement of Non-destructive Examination Reliability for the In-service Inspection of Light Water Reactors Program sponsored by the Nuclear Regulatory Commission at Pacific Northwest Laboratory (PNL) are to (1) assess current ISI techniques and requirements for all pressure boundary systems and components, (2) determine if improvements to the requirements are needed, and (3) if necessary, develop recommendations for revising the applicable ASME Codes and regulatory requirements. In evaluating approaches that could be used to provide a technical basis for improved inservice inspection plans, PNL has developed and applied a method that uses results of probabilistic risk assessment (PRA) to establish piping system ISI requirements. In the PNL program, the feasibility of generic ISI requirements is being addressed in two phases. Phase I involves identifying and prioritizing the systems most relevant to plant safety. The results of these evaluations will be later consolidated into requirements for comprehensive inservice inspection of nuclear power plant components that will be developed in Phase II. This report presents Phase I evaluations for eight selected plants and attempts to compare these PRA-based inspection priorities with current ASME Section XI requirements for Class 1, 2 and 3 systems. These results show that there are generic insights that can be extrapolated from the selected plants to specific classes of light water reactors

  18. Surface Casting Defects Inspection Using Vision System and Neural Network Techniques

    Directory of Open Access Journals (Sweden)

    Świłło S.J.

    2013-12-01

    Full Text Available The paper presents a vision based approach and neural network techniques in surface defects inspection and categorization. Depending on part design and processing techniques, castings may develop surface discontinuities such as cracks and pores that greatly influence the material’s properties Since the human visual inspection for the surface is slow and expensive, a computer vision system is an alternative solution for the online inspection. The authors present the developed vision system uses an advanced image processing algorithm based on modified Laplacian of Gaussian edge detection method and advanced lighting system. The defect inspection algorithm consists of several parameters that allow the user to specify the sensitivity level at which he can accept the defects in the casting. In addition to the developed image processing algorithm and vision system apparatus, an advanced learning process has been developed, based on neural network techniques. Finally, as an example three groups of defects were investigated demonstrates automatic selection and categorization of the measured defects, such as blowholes, shrinkage porosity and shrinkage cavity.

  19. Tank waste remediation system nuclear criticality safety inspection and assessment plan

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

  20. Fuel visual inspection system of the RTMIII; Sistema de inspeccion visual de combustible del RTMIII

    Energy Technology Data Exchange (ETDEWEB)

    Delfin L, A.; Castaneda J, G.; Mazon R, R.; Aguilar H, F. [ININ, Km. 36.5 Carretera Mexico-Toluca, Ocoyoacac, 52245 Estado de Mexico (Mexico)]. e-mail: rmr@nuclear.inin.mx

    2007-07-01

    The International Atomic Energy Agency (IAEA) through the RLA/04/18 project, Management of Irradiated Fuel in Research Reactors, it recommended among other that the participant countries (Brazil, Argentina, Chile, Peru and Mexico), develop tools to assure the integrity of the nuclear fuels used in the research reactors. The TRIGA Mark lll reactor (RTMIII) of the ININ, designed and built a system of visual inspection, that it uses a high radiation camera and image digitalisation. The project considers safety conditions of the personnel that carried out the activities of visual inspection, for that which the tool dives in the pool of the RTMIII, being held by an end in the superior part of the aluminium liner of the Reactor like it is shown in the plane No. 1. The primordial unit of the system is the visual equipment that corresponds to a camera of the Hydro-Technologie (HYTEC) VSLT 410N mark, designed to work in atmospheres under the water and/or in places of high risk. The camera has an unit of motorized orientation of stainless steel that can be rotated unboundedly in both senses, with variable speed by means of a control lever from the control unit. Together to this orientation unit is found the camera head, the one which is contained in an unit of motorized inclination of stainless steel that can be rotated azimuthally up to 370 degrees in both senses. The operation conditions of the camera are the following ones, temperature: 0 to 50 C, dose speed: {<=} 50 rad/h, operation depth: {<=} 30 mts, humidity (control unit): {<=} 80%. From the control unit it is derived an external device plug-n-play TV-Usb Aver Media marks whose function is to decode the video signal sent by the control unit and to transmit it to the computer where the image is captured in picture or video that is analyzed later on with any software ad hoc, that in our case we use the Quantikov Image Analyzer program for Windows 98 of the Dr. Lucio C. M. Pinto from Brazil who participates in the RLA

  1. Using Modified Fagan Inspections to Control Rapid System Development

    Science.gov (United States)

    Griesel, M. A.; Welz, L. L.

    1994-01-01

    The Jet Propulsion Laboratory (JPL) has been developing new approaches to software and system development to shorten life cycle time and reduce total life-cycle cost, while maintaining product quality. One such approach has been taken by the Just-In-Time (JIT) Materiel Acquisition System Development Project.

  2. Evaluation of Internal Cracks and Collapse in Poplar Wood (Populus nigra during a Conventional Drying Process with Ultrasonic Inspection

    Directory of Open Access Journals (Sweden)

    Saeid ESHAGHI

    2012-05-01

    Full Text Available In this research, internal cracks and collapse of wood, formed during drying process, were measured using ultrasonic inspection. For this purpose, seven poplar (Populus nigra small blocks were dried, according to a time-based schedule. Ultrasonic waves� propagation velocity was measured at both parallel and perpendicular to grain directions, using Sylvatest ultrasound device, during kiln drying process. Results showed that in all dried blocks, waves� propagation velocity in the parallel direction was higher than in the perpendicular direction to grain. Ultrasonic waves� propagation test for non-destructive identification of internal cracks, which occurs in wood during drying process in the parallel direction, was more successful compared to the perpendicular direction. Using ultrasonic waves� propagation test for detection of collapse that occurs in wood during drying process was not useful.

  3. Evaluation of Internal Cracks and Collapse in Poplar Wood (Populus nigra during a Conventional Drying Process with Ultrasonic Inspection

    Directory of Open Access Journals (Sweden)

    Saeid ESHAGHI

    2012-05-01

    Full Text Available In this research, internal cracks and collapse of wood, formed during drying process, were measured using ultrasonic inspection. For this purpose, seven poplar (Populus nigra small blocks were dried, according to a time-based schedule. Ultrasonic waves propagation velocity was measured at both parallel and perpendicular to grain directions, using Sylvatest ultrasound device, during kiln drying process. Results showed that in all dried blocks, waves propagation velocity in the parallel direction was higher than in the perpendicular direction to grain. Ultrasonic waves propagation test for non-destructive identification of internal cracks, which occurs in wood during drying process in the parallel direction, was more successful compared to the perpendicular direction. Using ultrasonic waves propagation test for detection of collapse that occurs in wood during drying process was not useful.

  4. Development of high sensitivity and high speed large size blank inspection system LBIS

    Science.gov (United States)

    Ohara, Shinobu; Yoshida, Akinori; Hirai, Mitsuo; Kato, Takenori; Moriizumi, Koichi; Kusunose, Haruhiko

    2017-07-01

    The production of high-resolution flat panel displays (FPDs) for mobile phones today requires the use of high-quality large-size photomasks (LSPMs). Organic light emitting diode (OLED) displays use several transistors on each pixel for precise current control and, as such, the mask patterns for OLED displays are denser and finer than the patterns for the previous generation displays throughout the entire mask surface. It is therefore strongly demanded that mask patterns be produced with high fidelity and free of defect. To enable the production of a high quality LSPM in a short lead time, the manufacturers need a high-sensitivity high-speed mask blank inspection system that meets the requirement of advanced LSPMs. Lasertec has developed a large-size blank inspection system called LBIS, which achieves high sensitivity based on a laser-scattering technique. LBIS employs a high power laser as its inspection light source. LBIS's delivery optics, including a scanner and F-Theta scan lens, focus the light from the source linearly on the surface of the blank. Its specially-designed optics collect the light scattered by particles and defects generated during the manufacturing process, such as scratches, on the surface and guide it to photo multiplier tubes (PMTs) with high efficiency. Multiple PMTs are used on LBIS for the stable detection of scattered light, which may be distributed at various angles due to irregular shapes of defects. LBIS captures 0.3mμ PSL at a detection rate of over 99.5% with uniform sensitivity. Its inspection time is 20 minutes for a G8 blank and 35 minutes for G10. The differential interference contrast (DIC) microscope on the inspection head of LBIS captures high-contrast review images after inspection. The images are classified automatically.

  5. Innovative inspection system for reactor pressure vessels; Innovative Pruefsysteme fuer Reaktordruckbehaelter

    Energy Technology Data Exchange (ETDEWEB)

    Mertens, K.; Trautmann, H.

    1999-08-01

    The versatile, compact and modern underwater systems described, the DELPHIN manipulators and MIDAS submarines, are innovative systems enabling RPV inspections at considerably reduced efforts and time, thus reducing the total time required for ISI of reactors. (orig./CB) [Deutsch] Die vorgestellten kleinen, flexiblen und modernen Schwimmsysteme (DELPHIN-Manipulatoren und MIDAS-U-Boote) sind innovative Systeme fuer die Reduzierung der Aufwaende und Zeit zur Pruefung des Reaktordruckbehaelters und damit zur Reduktion der Revisionszeiten der Reaktoranlagen. (orig.)

  6. Establishment of mobile based nuclear safety inspection system

    International Nuclear Information System (INIS)

    Kim, In Hyeon; Lee, Yoon; Choi, Keun Ho; Lee, Kwang Pyo; Cha, Gi Hyeon; Gook, Cheol Woong; Park, Tae Joo; Kang, Roc Hyeong; Kim, Ji Young; Yoo, Mi Jung

    2005-03-01

    We have developed the mobile-based atomic energy status real time monitoring system and mobile-based atomic energy accident and trouble retrieval system through this study. The mobile-based atomic energy status real time monitoring system is the system enabling its users to monitor nineteen (19) Nuclear Power Plants under operation in the real time based on the PDA(Personal Digital Assistance) via a wireless communication. We have developed the mobile information providing server program and PDA client program for the purpose of providing the atomic energy status information service on the PDA by linking the real time atomic energy status information collected by the computerized technical advisory system for the radiological emergency installed and operated by the KINS. The mobile based atomic energy accident and trouble retrieval system has been developed under the intention of enabling the site inspector to effectively use the past information upon performing the test works at the sites through the local retrieval of past accidents and troubles occurred in the Nuclear Power Plants at the mobile client(PDA). In this regard, we have developed the client program to retrieve the atomic energy accident and trouble status by installing the accident and trouble information database. We also include the function supporting the rapid site report through the employees' information retrieval, site status image file transmission, e-mail and SMS(Short Message Service)

  7. Qualification of UT methods and systems used for in-service inspections of VVER 440 vessels

    International Nuclear Information System (INIS)

    Skala, Z.; Vit, J.

    2003-01-01

    SKODA JS has been performing automated in-service inspections VVER reactor pressure vessels for more than twenty years. All of these inspections were performed by ultrasonic pulse echo method, combined from 1996 with eddy current testing. The Time of Flight Diffraction Method (TOFD) is one of modern methods of ultrasonic testing. The accuracy of sizing the through wall extent of a flaw by TOFD is much better than the accuracy achievable by the pulse echo method. A series of laboratory tests were performed by SKODA JS and confirmed the suitability of TOFD method for VVER reactor parts testing. The Czech Atomic law demands the qualification of systems and methods used for the in-service inspections of nuclear reactors. The qualification is done in accordance with ENIQ methodology and consists of preparation of the Technical Justification and practical tests made under the surveillance of Qualification Body. SKODA JS intends to qualify systems and methods used for the automated ultrasonic testing of VVER 440 and VVER 1000 reactor components from the inner as well as from the outer surface. The accuracy of the flaw through wall extent sizing by TOFD was confirmed by the qualification of methods and systems used for the testing of VVER 440 vessel circumferential weld and so the TOFD method shall be used routinely by SKODA JS for the inspection of vessel circumferential welds root area and for sizing of flaws exceeding the acceptance level. (author)

  8. Nondestructive web thickness measurement of micro-drills with an integrated laser inspection system

    Science.gov (United States)

    Chuang, Shui-Fa; Chen, Yen-Chung; Chang, Wen-Tung; Lin, Ching-Chih; Tarng, Yeong-Shin

    2010-09-01

    Nowadays, the electric and semiconductor industries use numerous micro-drills to machine micro-holes in printed circuit boards. The measurement of web thickness of micro-drills, a key parameter of micro-drill geometry influencing drill rigidity and chip-removal ability, is quite important to ensure quality control. Traditionally, inefficiently destructive measuring method is adopted by inspectors. To improve quality and efficiency of the web thickness measuring tasks, a nondestructive measuring method is required. In this paper, based on the laser micro-gauge (LMG) and laser confocal displacement meter (LCDM) techniques, a nondestructive measuring principle of web thickness of micro-drills is introduced. An integrated laser inspection system, mainly consisting of a LMG, a LCDM and a two-axis-driven micro-drill fixture device, was developed. Experiments meant to inspect web thickness of micro-drill samples with a nominal diameter of 0.25 mm were conducted to test the feasibility of the developed laser inspection system. The experimental results showed that the web thickness measurement could achieve an estimated repeatability of ± 1.6 μm and a worst repeatability of ± 7.5 μm. The developed laser inspection system, combined with the nondestructive measuring principle, was able to undertake the web thickness measuring tasks for certain micro-drills.

  9. System of leak inspection of irradiated fuel; Sistema de inspeccion de fuga de combustible irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Delfin L, A.; Castaneda J, G.; Mazon R, R.; Aguilar H, F. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: rmr@nuclear.inin.mx

    2007-07-01

    The International Atomic Energy Agency (IAEA) through the project RLA/04/18 Irradiated Fuel Management in Research reactors, recommended among other that the participant countries (Brazil, Argentina, Chile, Peru and Mexico), develop the sipping tool to generate registrations of the state that keep the irradiated fuels in the facilities of each country. The TRIGA Mark lll Reactor (RTMIII) Department, generated a project that it is based on the dimensions of the used fuel by the RTMIII, for design and to build an inspection system of irradiated fuel well known as SIPPING. This technique, provides a high grade of accuracy in the detection of gassy fission products or liquids that escape from the enveloping of fuels that have flaws or flights. The operation process of the SIPPING is carried out generating the migration of fission products through the creation of a pressure differential gas or vacuum to identify fuel assemblies failed by means of the detection of the xenon and/or krypton presence. The SIPPING system, is a device in revolver form with 4 tangential nozzles, which will discharge the fluid between the external surface of the enveloping of the fuel and the interior surface of the encircling one; the device was designed with independent pieces, with threaded joining and with stamps to impede flights of the fluid toward the exterior of the system. The System homogenizes and it distributes the fluid pressure so that the 4 nozzles work to equality of conditions, for what the device was designed in 3 pieces, an internal that is denominated revolver, one external that calls cover, and a joining called mamelon that will unite with the main encircling of the system. The detection of fission products in failed fuels, its require that inside the encircling one where the irradiated fuel element is introduced, be generated a pressure differential of gas or vacuum, and that it allows the samples extraction of water. For what generated a top for the encircling with the

  10. 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

  11. Proposal of a national system to supervise nuclear installations out of international safeguards

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-01-01

    It is proposed a national system to safeguard, supervise and inspect nuclear facilities in Brazil, apart from international safeguards. It discusses also the military nuclear activities and the uranium enrichment plants. The system should be controlled by Brazilian CNEN. (A.C.A.S.)

  12. Development of data management system for steam generator inspection

    International Nuclear Information System (INIS)

    Jung, Yong Moo; Im, Chang Jae; Lee, Yoon Sang; Kang, Soon Joo; An, Jong Kwan

    1994-06-01

    The data communications environment for transferring Nuclear Power Plant Steam Generator Eddy Current testing data was investigated and after connecting LAN to Hinet-F network, the remote data transfer with the speed of 56 kbps was tested successfully. Data management system for Steam Generator Eddy current testing was also developed by using HP-UX, RMB (Rock Mountain Basic) 21 figs, 13 tabs, 5 refs. (Author)

  13. Development of data management system for steam generator inspection

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Yong Moo; Im, Chang Jae; Lee, Yoon Sang; Kang, Soon Joo; An, Jong Kwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    The data communications environment for transferring Nuclear Power Plant Steam Generator Eddy Current testing data was investigated and after connecting LAN to Hinet-F network, the remote data transfer with the speed of 56 kbps was tested successfully. Data management system for Steam Generator Eddy current testing was also developed by using HP-UX, RMB (Rock Mountain Basic) 21 figs, 13 tabs, 5 refs. (Author).

  14. A whole process quality control system for energy measuring instruments inspection based on IOT technology

    Science.gov (United States)

    Yin, Bo; Liu, Li; Wang, Jiahan; Li, Xiran; Liu, Zhenbo; Li, Dewei; Wang, Jun; Liu, Lu; Wu, Jun; Xu, Tingting; Cui, He

    2017-10-01

    Electric energy measurement as a basic work, an accurate measurements play a vital role for the economic interests of both parties of power supply, the standardized management of the measurement laboratory at all levels is a direct factor that directly affects the fairness of measurement. Currently, the management of metering laboratories generally uses one-dimensional bar code as the recognition object, advances the testing process by manual management, most of the test data requires human input to generate reports. There are many problems and potential risks in this process: Data cannot be saved completely, cannot trace the status of inspection, the inspection process isn't completely controllable and so on. For the provincial metrology center's actual requirements of the whole process management for the performance test of the power measuring appliances, using of large-capacity RF tags as a process management information media, we developed a set of general measurement experiment management system, formulated a standardized full performance test process, improved the raw data recording mode of experimental process, developed a storehouse automatic inventory device, established a strict test sample transfer and storage system, ensured that all the raw data of the inspection can be traced back, achieved full life-cycle control of the sample, significantly improved the quality control level and the effectiveness of inspection work.

  15. Assessing risk factors in the organic control system: evidence from inspection data in Italy.

    Science.gov (United States)

    Zanoli, Raffaele; Gambelli, Danilo; Solfanelli, Francesco

    2014-12-01

    Certification is an essential feature in organic farming, and it is based on inspections to verify compliance with respect to European Council Regulation-EC Reg. No 834/2007. A risk-based approach to noncompliance that alerts the control bodies to activate planning inspections would contribute to a more efficient and cost-effective certification system. An analysis of factors that can affect the probability of noncompliance in organic farming has thus been developed. This article examines the application of zero-inflated count data models to farm-level panel data from inspection results and sanctions obtained from the Ethical and Environmental Certification Institute, one of the main control bodies in Italy. We tested many a priori hypotheses related to the risk of noncompliance. We find evidence of an important role for past noncompliant behavior in predicting future noncompliance, while farm size and the occurrence of livestock also have roles in an increased probability of noncompliance. We conclude the article proposing that an efficient risk-based inspection system should be designed, weighting up the known probability of occurrence of a given noncompliance according to the severity of its impact. © 2014 Society for Risk Analysis.

  16. Cooperative Behaviours with Swarm Intelligence in Multirobot Systems for Safety Inspections in Underground Terrains

    Directory of Open Access Journals (Sweden)

    Chika Yinka-Banjo

    2014-01-01

    Full Text Available Underground mining operations are carried out in hazardous environments. To prevent disasters from occurring, as often as they do in underground mines, and to prevent safety routine checkers from disasters during safety inspection checks, multirobots are suggested to do the job of safety inspection rather than human beings and single robots. Multirobots are preferred because the inspection task will be done in the minimum amount of time. This paper proposes a cooperative behaviour for a multirobot system (MRS to achieve a preentry safety inspection in underground terrains. A hybrid QLACS swarm intelligent model based on Q-Learning (QL and the Ant Colony System (ACS was proposed to achieve this cooperative behaviour in MRS. The intelligent model was developed by harnessing the strengths of both QL and ACS algorithms. The ACS optimizes the routes used for each robot while the QL algorithm enhances the cooperation between the autonomous robots. A description of a communicating variation within the QLACS model for cooperative behavioural purposes is presented. The performance of the algorithms in terms of without communication, with communication, computation time, path costs, and the number of robots used was evaluated by using a simulation approach. Simulation results show achieved cooperative behaviour between robots.

  17. Compact and air-transportable ultrasonic turbine disc bore inspection system

    International Nuclear Information System (INIS)

    Larsen, R.E.; Leon-Salamanca, T.

    1990-01-01

    A compact, lightweight, air-transportable ultrasonic inspection system for bore and keyway regions of shrunk-on turbine discs has been developed. The system utilizes a proprietary ultrasound liquid coupling technique in conjunction with a single pair of gimballed search units to achieve rapid and thorough coverage of bores and keyways in both heavy nuclear and standard fossil discs of nearly any size and having any conceivable web surface contour. Search unit positioning and angulation parameter settings are established in near real-time through a computation algorithm based on a compact vector ray tracing protocol. Modular construction and the use of lightweight, stiff materials throughout facilitates air shipment of the system and its rapid deployment at continental and overseas field sites. Mechanical and ultrasonic features of the system are described. Development and application of the computation algorithm to the ultrasonic inspection of heavy discs at an overseas power station is discussed

  18. VerifEYE: a real-time meat inspection system for the beef processing industry

    Science.gov (United States)

    Kocak, Donna M.; Caimi, Frank M.; Flick, Rick L.; Elharti, Abdelmoula

    2003-02-01

    Described is a real-time meat inspection system developed for the beef processing industry by eMerge Interactive. Designed to detect and localize trace amounts of contamination on cattle carcasses in the packing process, the system affords the beef industry an accurate, high speed, passive optical method of inspection. Using a method patented by United States Department of Agriculture and Iowa State University, the system takes advantage of fluorescing chlorophyll found in the animal's diet and therefore the digestive track to allow detection and imaging of contaminated areas that may harbor potentially dangerous microbial pathogens. Featuring real-time image processing and documentation of performance, the system can be easily integrated into a processing facility's Hazard Analysis and Critical Control Point quality assurance program. This paper describes the VerifEYE carcass inspection and removal verification system. Results indicating the feasibility of the method, as well as field data collected using a prototype system during four university trials conducted in 2001 are presented. Two successful demonstrations using the prototype system were held at a major U.S. meat processing facility in early 2002.

  19. Conduct of inspections for plant modifications, event investigations and operability decisions. Proceedings of an International Workshop

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    Preliminary planning started following the approval given by the CNRA. Formal planning for the Workshop was started at the Fifth Meeting of the WGIP in April 1993, in Lyon. Planning included taking into consideration comments made and lessons learned at the first Workshop. The first organising committee meeting for the Workshop was held in London preceding the Sixth WGIP meeting in October 1993. It was decided to remain with the same format: discussion groups with facilitators. It was also decided to have a three day programme with three Discussion Group sessions. The Announcement and Call for Participation was issued in December 1993. As part of the Announcement and Call for Participation, registrants were requested to transmit questions or issues of particular interest within the selected topics, they wanted to be addressed at the Workshop. A compilation of the these is included as Appendix H. Additionally, participants were requested to provide a short paper of one or two pages, describing the practices within their own countries related to the topics, for utilisation during the discussion sessions. These papers are attached as Appendix I. A training session was held for all facilitators on the afternoon of 22 May, to introduce methods in leading small group discussions and to complete final preparations. The Workshop programme (Appendix B) consisted of an opening plenary session, 3 discussion group sessions and a closing plenary session to review conclusions and an open question period. Following completion of the Workshop, facilitators met to evaluate and formulate final reports on the various topics. The main objectives of the Workshop were the following: To meet with inspectors from other organisations, To exchange information regarding regulatory inspections practices, To discuss the major topics: plant modifications, event investigation, and operability decisions, To discuss current issues, To develop conclusions on the topics discussed. Six discussion

  20. Conduct of inspections for plant modifications, event investigations and operability decisions. Proceedings of an International Workshop

    International Nuclear Information System (INIS)

    1995-01-01

    Preliminary planning started following the approval given by the CNRA. Formal planning for the Workshop was started at the Fifth Meeting of the WGIP in April 1993, in Lyon. Planning included taking into consideration comments made and lessons learned at the first Workshop. The first organising committee meeting for the Workshop was held in London preceding the Sixth WGIP meeting in October 1993. It was decided to remain with the same format: discussion groups with facilitators. It was also decided to have a three day programme with three Discussion Group sessions. The Announcement and Call for Participation was issued in December 1993. As part of the Announcement and Call for Participation, registrants were requested to transmit questions or issues of particular interest within the selected topics, they wanted to be addressed at the Workshop. A compilation of the these is included as Appendix H. Additionally, participants were requested to provide a short paper of one or two pages, describing the practices within their own countries related to the topics, for utilisation during the discussion sessions. These papers are attached as Appendix I. A training session was held for all facilitators on the afternoon of 22 May, to introduce methods in leading small group discussions and to complete final preparations. The Workshop programme (Appendix B) consisted of an opening plenary session, 3 discussion group sessions and a closing plenary session to review conclusions and an open question period. Following completion of the Workshop, facilitators met to evaluate and formulate final reports on the various topics. The main objectives of the Workshop were the following: To meet with inspectors from other organisations, To exchange information regarding regulatory inspections practices, To discuss the major topics: plant modifications, event investigation, and operability decisions, To discuss current issues, To develop conclusions on the topics discussed. Six discussion

  1. INIS - International Nuclear Information System

    International Nuclear Information System (INIS)

    Nevyjel, A.

    1983-10-01

    The International Nuclear Information System is operated by the IAEA in close cooperation with its participating countries. Each country is responsible for the acquisition of the literature published within its boundaries. These data are collected by the INIS secretariat in Vienna and the resulting comprehensive data base is available for all member states. On behalf of Austrian Federal Chancellor's Office the Austrian Research Centre Seibersdorf operates the Austrian INIS-Center, which offers information services in form of retrospective searches and current awareness services. (Author) [de

  2. Development of a Multi-Channel Ultrasonic Testing System for Automated Ultrasonic Pipe Inspection of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lee, Hee Jong; Cho, Chan Hee; Cho, Hyun Joon

    2009-01-01

    Currently almost all in-service-inspection techniques, applied in domestic nuclear power plants, are partial to field inspection technique. These kinds of techniques are related to managing nuclear power plants by the operation of foreign-produced inspection devices. There have been so many needs for development of native in-service-inspection device because there is no native diagnosis device for nuclear power plant inspection yet in Korea. In this research, we developed several core techniques to make an automated ultrasonic pipe inspection system for nuclear power plants. A high performance multi-channel ultrasonic pulser/receiver module, an A/D converter module and a digital main CPU module were developed and the performance of the developed modules was verified. The S/N ratio, noise level and signal acquisition performance of the developed modules showed proper level as we designed in the beginning.

  3. Research on the Application of Risk-based Inspection for the Boiler System in Power Plant

    Science.gov (United States)

    Li, Henan

    2017-12-01

    Power plant boiler is one of the three main equipment of coal-fired power plants, is very tall to the requirement of the safe and stable operation, in a significant role in the whole system of thermal power generation, a risk-based inspection is a kind of pursuit of security and economy of unified system management idea and method, can effectively evaluate equipment risk and reduce the operational cost.

  4. 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.)

  5. Energy Storage System Safety: Plan Review and Inspection Checklist

    Energy Technology Data Exchange (ETDEWEB)

    Cole, Pam C (PNNL); Conover, David R (PNNL)

    2017-03-01

    Codes, standards, and regulations (CSR) governing the design, construction, installation, commissioning, and operation of the built environment are intended to protect the public health, safety, and welfare. While these documents change over time to address new technology and new safety challenges, there is generally some lag time between the introduction of a technology into the market and the time it is specifically covered in model codes and standards developed in the voluntary sector. After their development, there is also a timeframe of at least a year or two until the codes and standards are adopted. Until existing model codes and standards are updated or new ones are developed and then adopted, one seeking to deploy energy storage technologies or needing to verify the safety of an installation may be challenged in trying to apply currently implemented CSRs to an energy storage system (ESS). The Energy Storage System Guide for Compliance with Safety Codes and Standards1 (CG), developed in June 2016, is intended to help address the acceptability of the design and construction of stationary ESSs, their component parts, and the siting, installation, commissioning, operations, maintenance, and repair/renovation of ESS within the built environment.

  6. A Study on Adaptable Non-contact Shape Inspection System

    International Nuclear Information System (INIS)

    Kang, Young June; Park, Nak Gyu; Lee, Dong Hwan

    2005-01-01

    A new dimension measuring method for the measurement of diameter of an object has been developed using laser triangulation. The 3D data of an object was calculated from the 2 dimensional image information obtained by the laser stripe using the laser triangulation. The system that use existing theory can measure the diameter of hole not only in a normal plane but also ill an incline plane. However, in the existing theory, since the lens with fixed feral length was used, the area of measurement was fixed. The simplest way to solve this problem is to change distance between a CCD camera and object. Other way is to use a zoom lens having variable focal length. In this paper, the zoom lens with variable focal length was used. Therefore, we ran experiment with magnification that is optimized according to size of object using zoom lens with variable focal length

  7. Nuclear containment systems and in-service inspection status of Korea nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jihong, Park; Jaekeun, Hong; Banuk, Park [Korea Institute of Machinery and Materials, Dept. of Authorized Test and Evaluation, Kyungnam (Korea, Republic of)

    2007-07-01

    20 unit nuclear power plants in Korea have been operated and maintained since the first unit started in commercial service in 1978. Most recently 4 units were under construction and several units were planned to be constructed. by industries. 4 types of nuclear containment systems have been constructed until now: first, metal containments, then pre-stressed concrete containments with grouted tendon systems, followed by pre-stressed concrete containments with un-grouted tendon systems, and Korea standard nuclear containments. All the nuclear containments should be inspected periodically. Therefore for periodic in-service inspection, several appropriate technical requirements should be applied differently depending on the specific nuclear containment types. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally nuclear containment system of Korea standard nuclear power plant was settled down, and as a matter of course it dominates the trend of present and future nuclear containment systems. Overall in-service inspection results of most Korea nuclear containments have not showed any serious evidence of degradation.

  8. Development of CANDU fuel in-bay inspection and dimensional measurement system

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Chang Keun; Cho, Moon Sung; Suk, Ho Chun; Koo, Dae Seo; Park, Kwang June; Jun, Ji Su; Jung, Jong Yeob

    2004-09-01

    In this report, we describe a spent fuel inspection and dimensional measuring system for CANDU fuel bundles in atmosphere or water. The submissible camera with radiation resistance was used to inspect a spent fuel in water. The design criteria of the dimensional measuring system was set up {+-}0.01mm(10{mu}m) for measuring accuracy. The LVDT (Linear Variable Differential Transformer) was used as measuring sensor in this dimensional measuring system. An LVDT calibration equipment was developed in order to satisfy the required accuracy of the system. Also, aluminum master and CANDU Master with same dimension of fuel bundle was made to calibrate the mechanical error of the dimensional measuring system. The accuracy of the fuel inspection system was examined. The results show that the accuracy in dimensional measurement of fuel rod profile and bearing pad profile, diameter of fuel bundle, fuel rod length, and end plate profile using standard test equipment satisfies the design criteria, i.e., maximum measurement error of {+-}0.01mm(10{mu}m)

  9. Effect of a Publicly Accessible Disclosure System on Food Safety Inspection Scores in Retail and Food Service Establishments.

    Science.gov (United States)

    Choi, Jihee; Scharff, Robert L

    2017-07-01

    The increased frequency with which people are dining out coupled with an increase in the publicity of foodborne disease outbreaks has led the public to an increased awareness of food safety issues associated with food service establishments. To accommodate consumer needs, local health departments have increasingly publicized food establishments' health inspection scores. The objective of this study was to estimate the effect of the color-coded inspection score disclosure system in place since 2006 in Columbus, OH, by controlling for several confounding factors. This study incorporated cross-sectional time series data from food safety inspections performed from the Columbus Public Health Department. An ordinary least squares regression was used to assess the effect of the new inspection regime. The introduction of the new color-coded food safety inspection disclosure system increased inspection scores for all types of establishments and for most types of inspections, although significant differences were found in the degree of improvement. Overall, scores increased significantly by 1.14 points (of 100 possible). An exception to the positive results was found for inspections in response to foodborne disease complaints. Scores for these inspections declined significantly by 10.2 points. These results should be useful for both food safety researchers and public health decision makers.

  10. Radiography simulation on single-shot dual-spectrum X-ray for cargo inspection system

    International Nuclear Information System (INIS)

    Gil, Youngmi; Oh, Youngdo; Cho, Moohyun; Namkung, Won

    2011-01-01

    We propose a method to identify materials in the dual energy X-ray (DeX) inspection system. This method identifies materials by combining information on the relative proportions T of high-energy and low-energy X-rays transmitted through the material, and the ratio R of the attenuation coefficient of the material when high-energy are used to that when low energy X-rays are used. In Monte Carlo N-Particle Transport Code (MCNPX) simulations using the same geometry as that of the real container inspection system, this T vs. R method successfully identified tissue-equivalent plastic and several metals. In further simulations, the single-shot mode of operating the accelerator led to better distinguishing of materials than the dual-shot system.

  11. 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...

  12. 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...

  13. FY 1999 project on the development of new industry support type international standards. Standards development of chemical analysis and non-destructive inspection methods for pure titanium metals; 1999 nendo shinki sangyo shiengata kokusai hyojun kaihatsu jigyo seika hokokusho. Junchitan no shiken hyoka hoho no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    To propose it to ISOTC79 and ISOTC135, study was conducted for standardization of chemical analysis method and non-destructive inspection method for industrial use pure titanium. As the chemical analysis method, the inductively coupled plasma atomic emission spectrometry which has good detection limit was developed, and at the same time, the standardization of spark and/or glow discharged atomic emission spectrometry was developed. As the non-destructive inspection method, developmental study on the following was carried out: surface defect inspection method of pure titanium metals by laser scanning inspection system or CCD camera; internal defect inspection of pure titanium sheet and coil by plate wave ultrasonic inspection method; internal defect inspection of pure titanium bar by eddy current method; inspection of very small leakage of pressurized fluid through defects in pure titanium pipe and tube by pressure differential testing method. As a result of the study, standards of system performance and tolerance were determined in analysis of Pd, Si, Al, Cu, Mo, Zr, Nb, Ta and Y. Further, analytical conditions and application ranges of the spark discharged atomic emission spectrometry were made definite in terms of 19 elements including Mn, Fe, Ni, Cr, Sn, Pb, Si, Al, V, Cu, Mo, Zr, Nb, Ta, Co, B, Y, C and W. (NEDO)

  14. A Robotic System for Inspection and Repair of Small Diameter Pipelines

    Directory of Open Access Journals (Sweden)

    S. A. Vorotnikov

    2015-01-01

    Full Text Available This paper deals with the construction and control system of miniature robotic system that is designed to move and make inspection inside small diameter pipelines. It gives an overview of ways to move a microsize robotic system inside the small diameter pipe. The proposed design consists of information module and three traction modules, including modules for fixing, linear moving and angular positioning. This paper describes the design and operation of a robotic system and its different modules. Also are shown the structure of the robot control system, the basic calculations of construct and some simulation results of the individual modules of the robot.

  15. 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...

  16. International safeguards data management system

    International Nuclear Information System (INIS)

    Argentesi, F.; Costantini, L.; Franklin, M.; Dondi, M.G.

    1981-01-01

    The data base management system ''ISADAM'' (i.e. International Safeguards Data Management System) described in this report is intended to facilitate the safeguards authority in making efficient and effective use of accounting reports. ISADAM has been developed using the ADABAS data base management system and is implemented on the JRC-Ispra computer. The evaluation of safeguards declarations focuses on three main objectives: - the requirement of syntactical consistency with the legal conventions of data recording for safeguards accountancy; - the requirement of accounting evidence that there is no material unaccounted for (MUF); - the requirement of semantic consistency with the technological characteristics of the plant and the processing plans of the operator. Section 2 describes in more detail the facilities which ISADAM makes available to a safeguards inspector. Section 3 describes how the MUF variance computation is derived from models of measurement error propagation. Many features of the ISADAM system are automatically provided by ADABAS. The exceptions to this are the utility software designed to: - screen plant declarations before loading into the data base, - prepare variance summary files designed to support real-time computation of MUF and variance of MUF, - provide analyses in response to user requests in interactive or batch mode. Section 4 describes the structure and functions of this software which have been developed by JRC-Ispra

  17. A brick-architecture-based mobile under-vehicle inspection system

    Science.gov (United States)

    Qian, Cheng; Page, David; Koschan, Andreas; Abidi, Mongi

    2005-05-01

    In this paper, a mobile scanning system for real-time under-vehicle inspection is presented, which is founded on a "Brick" architecture. In this "Brick" architecture, the inspection system is basically decomposed into bricks of three kinds: sensing, mobility, and computing. These bricks are physically and logically independent and communicate with each other by wireless communication. Each brick is mainly composed by five modules: data acquisition, data processing, data transmission, power, and self-management. These five modules can be further decomposed into submodules where the function and the interface are well-defined. Based on this architecture, the system is built by four bricks: two sensing bricks consisting of a range scanner and a line CCD, one mobility brick, and one computing brick. The sensing bricks capture geometric data and texture data of the under-vehicle scene, while the mobility brick provides positioning data along the motion path. Data of these three modalities are transmitted to the computing brick where they are fused and reconstruct a 3D under-vehicle model for visualization and danger inspection. This system has been successfully used in several military applications and proved to be an effective safer method for national security.

  18. Benefits And Humanisation Of The Working Environment By Using Laser Inspection Systems In The Industry

    Science.gov (United States)

    Mueller, Peter; Pietzsch, Karl; Feige, Christian

    1989-02-01

    At a time of rapid development, introduction of new technologies, and increasing world-wide competition, the quality specifications for products and materials becoming even more demanding. This also applies with regard to the avoidance of defects in the surfaces of materials. Consequently there is a need for systems which allow 100% in-line testing of materials and surfaces during the production of, e.g. textiles, data storage media, papers, films and metals. Thanks to its optical and electronical precision, its unlimited applications - even under the most severe conditions-and its absolutely constant acuity, compared with visual inspection, the Sick-Scan-System is an excellent means for improving quality and profits in industrial manufacture, reducing rejects production and thus providing even more customer satisfaction. Here we describe briefly our laser scanner technology. It will set new standards in the area of automatic inspection, and the term laser tested will stablish itself as a mark of quality. In the last few years laser scanning inspection systems have been further developed in collaboration with a large number of materials manufacturers. These systems have been adopted in modern production lines and demonstrate their economy.

  19. Automation of eddy current system for in-service inspection of turbine and generator bores

    International Nuclear Information System (INIS)

    Viertl, J.R.M.

    1988-01-01

    The most commonly applied inspection method for ferromagnetic turbine and generator rotor bores is the magnetic particle test technique. This method is subjective, depends on the test operator's skill and diligence in identifying test indications, and suffers from poor repeatability, especially for small indications. Automation would improve repeatability. However, magnetic particle tests are not easily automated, because the data are in the form of sketches, photographs, and written and oral descriptions of the indications. Eddy current inspection has obvious potential to replace magnetic particle methods in this application. Eddy current tests can be readily automated, as the data are in the form of voltages that can be recorded, digitized, and manipulated by a computer. The current project continues the investigation of the correlation between eddy current and magnetic particle inspection. Two systems have been combined to acquire eddy current data automatically. This combination of systems consists of the Nortec-25L Eddyscope (to provide the analog eddy current signals) and the General Electric DATAQ (TM) System (to perform the automatic data acquisition). The automation of the system is discussed

  20. 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.)

  1. Multifrequency eddy-current system for inspection of steam generator turbine

    International Nuclear Information System (INIS)

    Davis, T.J.

    1980-11-01

    The objectives of this program were to: determine the maximum advantage of the multifrequency eddy current method for nuclear steam generator tubing inspection; simplify system operating procedures and enhance presentation of mutifrequency data; and evaluate multifrequency methods for inspecting recently encountered types of anomalies such as circumferential cracks, inside diameter flaws, and flaws in dented regions. New test methods developed under the program have resulted in a dramatic improvement over earlier multifrequency work. The methods rely on judicious selection of test frequencies and the simultaneous use of differential and absolute multiparameter inspection. Flaws may be sized and profiled with increased accuracy over that of the single-frequency method, and improved rejection of indications from unwanted parameters such as support plates and probe wobble has been obtained. The ability to detect and size support cracks in both corroded and non-corroded supports has been demonstrated on a laboratory basis. A field-usable test system employing four test frequencies was developed under the program and has been evaluated in the EPRI steam generator mockup. Some of the new technology used in this system has been commercialized into the new Zetec MIZ-12 multifrequency system

  2. Condition Assessment Survey (CAS) Program. Deficiency standards and inspections methods manual: Volume 11, 0.11 Specialty systems

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    General information is presented for asset determinant factor/CAS repair codes/CAS cost factors; guide sheet tool & material listing; testing methods; inspection frequency; standard system design life tables; system work breakdown structure; and general system/material data. Deficiency standards and inspection methods are presented for canopies; loading dock systems; tanks; domes (bulk storage, metal framing); louvers & vents; access floors; integrated ceilings; and mezzanine structures.

  3. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    Energy Technology Data Exchange (ETDEWEB)

    Caffrey, Gus J. [Idaho National Laboratory, Idaho Falls, ID (United States); Egger, Ann E. [Idaho National Laboratory, Idaho Falls, ID (United States); Krebs, Kenneth M. [Idaho National Laboratory, Idaho Falls, ID (United States); Milbrath, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jordan, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Warren, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilmer, N. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  4. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    International Nuclear Information System (INIS)

    Caffrey, Gus J.; Egger, Ann E.; Krebs, Kenneth M.; Milbrath, B. D.; Jordan, D. V.; Warren, G. A.; Wilmer, N. G.

    2015-01-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-Osiris-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  5. ANALYSIS OF PERIODICAL TECHNICAL INSPECTION SYSTEMS IN AUTOMOTIVE TRANSPORT. THE EXPERIENCES OF POLAND AND RUSSIA

    Directory of Open Access Journals (Sweden)

    Jan FILIPCZYK

    2015-12-01

    Full Text Available The increasing number of road accidents nowadays seems to by a global problem. Apart from the obvious causes of accidents, such as violation of road traffic rules by drivers and pedestrians, the drunk driving, poor quality of road infrastructure, the technical faults of vehicles should also be take into account. Reasons of technical failures can be the failure of parts, components and assemblies caused by aging, poor quality or non-observance of technological norms when they are installed. It is possible to prevent the occurrence of faults by applying warning methods, one of which is obligatory periodic technical inspection. The purpose of this article is to analyze the characteristic features of the systems of technical inspections in automotive transport used in Poland and Russia. It makes it possible to identify common features and distinctive features of systems in both countries.

  6. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    International Nuclear Information System (INIS)

    Wong, S.; DiBiasio, A.; Gunther, W.

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant

  7. High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Wong, S.; DiBiasio, A.; Gunther, W. [Brookhaven National Lab., Upton, NY (United States)

    1993-09-01

    The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

  8. Review of P-scan computer-based ultrasonic inservice inspection system. Supplement 1

    International Nuclear Information System (INIS)

    Harris, R.V. Jr.; Angel, L.J.

    1995-12-01

    This Supplement reviews the P-scan system, a computer-based ultrasonic system used for inservice inspection of piping and other components in nuclear power plants. The Supplement was prepared using the methodology described in detail in Appendix A of NUREG/CR-5985, and is based on one month of using the system in a laboratory. This Supplement describes and characterizes: computer system, ultrasonic components, and mechanical components; scanning, detection, digitizing, imaging, data interpretation, operator interaction, data handling, and record-keeping. It includes a general description, a review checklist, and detailed results of all tests performed

  9. Remote inspection of a buried pipeline using a mobile ultrasonic testing system

    Energy Technology Data Exchange (ETDEWEB)

    Muralidhar, S; Ghosh, J K [Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.; Rajendran, S; Ramakumar, M S [Bhabha Atomic Research Centre, Mumbai (India). Division of Remote Handling and Robotics

    1994-12-31

    The nuclear reactor, Cirus, has now been in operation for three decades. As part of a programme to ascertain the integrity and safety of the various reactor parts in-service inspection of the embedded portion of the main coolant pipeline will be carried out. A mobile ultrasonic testing system has been developed and tested in the laboratory to measure the wall thickness of an underground pipe from the inner corroded surface using a water-bubbler technique. 3 figs.

  10. Major upgrade of the articulated inspection arm control system to fulfill daily operation requirements

    Energy Technology Data Exchange (ETDEWEB)

    Pastor, P., E-mail: patrick.pastor@cea.fr [CEA, IRFM, Institut de Recherche sur la Fusion par confinement Magnétique (France); Villedieu, E.; Allegretti, L.; Vincent, B.; Barbuti, A.; Bruno, V.; Coquillat, P.; Dechelle, C.; Gargiulo, L.; Le, R.; Malard, P.; Martinez, A.; Nouailletas, R. [CEA, IRFM, Institut de Recherche sur la Fusion par confinement Magnétique (France); Yuntao, Song; Yong, Cheng; Chen, Liu; Hansheng, Feng; Shanshuang, Shi [ASIPP, Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui (China)

    2015-10-15

    Highlights: • We propose an overview of the work which has been done to upgrade the control system of the AIA robot (articulated inspection arm) to fulfill daily operation requirements for tokamak inspection. • The control system is based on the use of new position sensors, new electronics design and new supervisor software. • Final tests are ongoing in the EAST scale 1 tokamak mock-up. Routine operation of the robot at EAST will start in the beginning of 2015. - Abstract: An articulated inspection arm (AIA) has been developed by CEA for visual inspection between pulses inside the Tore Supra tokamak vacuum vessel without breaking temperature and vacuum conditions. The eight meters length robot is composed of a shuttle and six articulated segments with a video camera at its end. A demonstration prototype has been achieved in 2008 at Tore Supra (Gargiulo, 2007; Houry, 2008; Perrot, 2003). A project to upgrade the AIA into a fully operational robot has been undertaken by IRFM and ASIPP in an Associated Laboratory. It will be in operation first in the EAST machine and afterwards in Tore Supra in its WEST (W/Tungsten Environment in Steady-state Tokamak) configuration where it is of paramount importance to survey possible degradation of W component surface. The control system of the robot has been extensively upgraded. The effort has been focused on three areas: (1) improvement of the arm position accuracy, (2) increase of the operational robustness, (3) use of a powerful graphical user interface including simulation of trajectories and robot deployment capabilities in a 3D viewer environment. The aim of this paper is to detail the architecture of the AIA control system.

  11. Remotely controlled inspection and handling systems for decommissioning tasks in nuclear facilities

    International Nuclear Information System (INIS)

    Schreck, G.; Bach, W.; Haferkamp, H.

    1993-01-01

    The Institut fur Werkstoffkunde at the University of Hanover has recently developed three remotely controlled systems for different underwater inspection and dismantling tasks. ODIN I is a tool guiding device, particularly being designed for the dismantling of the steam dryer housing of the KRB A power plant at Gundremmingen, Germany. After being approved by the licencing organization TUEV Bayern, hot operation started in November 1992. The seven axes remotely controlled handling system ZEUS, consisting of a three translatory axes guiding machine and a tool handling device with four rotatory axes, has been developed for the demonstration of underwater plasma arc cutting of spherical metallic components with great wall thicknesses. A specially designed twin sensor system and a modular torch, exchanged by means of a remote controlled tool changing device, will be used for different complex cutting tasks. FAUST, an autonomous, freediving underwater vehicle, was designed for complex inspection, maintenance and dismantling tasks. It is equipped with two video cameras, an ultrasonic and a radiologic sensor and a small plasma torch. A gripper and a subsidiary vehicle for inspection may be attached. (author)

  12. 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...

  13. 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

  14. International Responsibility and the Systemic Character of International Law

    Directory of Open Access Journals (Sweden)

    Saganek Przemysław

    2017-12-01

    Full Text Available The question whether international law is a system is one of the modern topics discussed by specialists of international law. The text of P. Saganek poses this question with respect to the rules on international responsibility. The two aims are to establish whether the rules on state responsibility are a system themselves and whether they may prima facie support the idea of international law as such a system. The two prima facie answers are positive. Every violation of international law gives rise to state responsibility if it can be attributed to a state and no circumstance precluding wrongfulness is in place. In this sense the rules on state responsibility form a sub-system supporting the thesis on the systemic nature of international law. On a closer analysis one can encounter several doubts as to both answers. Paradoxically those rules are too ideal, too systemic. The author – without denying the necessity of several if not the majority of the identified rules – refers to a tendency of presenting as law some non-binding documents prepared by expert groups. This is a part of a wider process of ‘paper-law’. In this sense expert groups engage in ‘creating the language’ in which the true subjects of international law are expected to speak.

  15. High energy X-ray CT system using a linear accelerator for automobile parts inspection

    International Nuclear Information System (INIS)

    Kanamori, T.; Sukita, T.

    1995-01-01

    A high energy X-ray CT system (maximum photon energy: 0.95 MeV) has been developed for industrial use. This system employs a linear accelerator as an X-ray source. It is able to image the cross section of automobile parts and can be applied to a solidification analysis study of the cylinder head in an automobile. This paper describes the features of the system and application results which can be related to solidification analysis of the cylinder head when fabricated from an aluminum casting. Some cross-sectional images are also presented as evidence for nondestructive inspection of automobile parts. (orig.)

  16. 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

  17. Internal frictions and their application in the supervision and inspection of a manufacture

    International Nuclear Information System (INIS)

    Bourgain, L.; Samson, G.; Blay, D.

    1975-01-01

    The internal frictions of materials subjected to flexion or compression waves were studied. In the first part of the report, devoted to the theoretical aspect of the problem, an attempt is made to estimate how much of the total friction measured is exterior to the structure and how much is intrinsic. The mathematical models generally used to account for these phenomena, those of Maxwell and Voigt, were applied for this purpose. Part two deals with measurement methods and precautions necessary if good precision and reproducible experimental results are required. The last part gives several examples of application. It is shown how internal damping measurements are used to detect variations in a given manufacture. In the application specific to sintered materials a physical explanation is tentatively put forward to account for the peaks recorded at middle frequency (between 1000 and 10000 hertz) in the damping spectrum; these are connected with interface phenomena between the grains, sometimes known as surface/volume effect [fr

  18. Development of an ultrasonic weld inspection system based on image processing and neural networks

    Science.gov (United States)

    Roca Barceló, Fernando; Jaén del Hierro, Pedro; Ribes Llario, Fran; Real Herráiz, Julia

    2018-04-01

    Several types of discontinuities and defects may be present on a weld, thus leading to a considerable reduction of its resistance. Therefore, ensuring a high welding quality and reliability has become a matter of key importance for many construction and industrial activities. Among the non-destructive weld testing and inspection techniques, the time-of-flight diffraction (TOFD) arises as a very safe (no ionising radiation), precise, reliable and versatile practice. However, this technique presents a relevant drawback, associated to the appearance of speckle noise that should be addressed. In this regard, this paper presents a new, intelligent and automatic method for weld inspection and analysis, based on TOFD, image processing and neural networks. The developed system is capable of detecting weld defects and imperfections with accuracy, and classify them into different categories.

  19. A Portable Ultrasonic Nondestructive Inspection System for Metal Matrix Composite Track Shoes

    International Nuclear Information System (INIS)

    Mi Bao; Zhao Xiaoliang; Qian Tao; Stevenson, Mark; Kwan, Chiman; Owens, Steven E.; Royer, Roger L. Jr.; Tittmann, Bernhard R.; Raju, Basavaraju B.

    2007-01-01

    Cast aluminum track shoes reinforced with metal matrix composite (MMC) inserts at heavy loading areas such as center splines and sprocket windows are light in weight, and can resist high temperature and wear. Various defects such as disbonds at the insert-substrate interface, cracks and porosity in the MMC layer, etc. can be introduced during the manufacturing process and/or in service. This paper presents a portable ultrasonic system to automatically inspect tank track shoes for disbond. Ultrasonic pulse/echo inspection has shown good reliability for disbond detection. A prototype sensor array fixture has been designed and fabricated to prove the feasibility. Good agreements between the sensor fixture results and ultrasonic C-scan images were obtained

  20. Auxiliary feedwater system risk-based inspection guide for the North Anna nuclear power plants

    International Nuclear Information System (INIS)

    Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1992-10-01

    In a study sponsored by the US Nuclear regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. North Anna was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the North Anna plant

  1. Documentation for initial testing and inspections of Beneficial Uses Shipping System (BUSS) Cask

    International Nuclear Information System (INIS)

    Lundeen, J.E.

    1994-01-01

    The purpose of this report is to compile data generated during the initial tests and inspections of the Beneficial Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in section 8.1 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The BUSS Cask body and lid are each one-piece forgings fabricated from ASTM A473, Type 304 stainless steel. The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Chapter 8 of the BUSS Cask SARP requires several acceptance tests and inspections, each intended to evaluate the performance of different components of the BUSS Cask system, to be performed before its first use. The results of the tests and inspections required are included in this document

  2. Auxiliary feedwater system risk-based inspection guide for the Palo Verde Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Sloan, J.A.

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Palo Verde was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Palo Verde plants

  3. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1994-05-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant

  4. Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

    International Nuclear Information System (INIS)

    Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1993-12-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant

  5. Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

    1992-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

  6. Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

    International Nuclear Information System (INIS)

    Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1991-07-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Byron/Braidwood plants. 23 refs., 1 fig., 1 tab

  7. Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

    International Nuclear Information System (INIS)

    Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V.; Garner, L.W.

    1993-08-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant

  8. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    International Nuclear Information System (INIS)

    Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.; Vehec, T.A.

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant

  9. Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

    International Nuclear Information System (INIS)

    Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E.

    1991-09-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab

  10. The International Atomic Energy Agency's safeguards system

    International Nuclear Information System (INIS)

    Wagner, W.

    2000-01-01

    A system of international safeguards has been established to provide assurance that nuclear materials in civilian use are not diverted from their peaceful purpose. The safeguards system is administered by the International Atomic Energy Agency/Department of Safeguards and devolves from treaties and other international agreements. Inspectors from the Agency verify reports from States about nuclear facilities by audits, observation, and measurements. (author)

  11. VEDS-Automated system for inspection of vehicles and containers for explosives and other threats

    International Nuclear Information System (INIS)

    Gozani, T.; Liu, F.; Sivakumar, M.

    2004-01-01

    Many parts of national infrastructures around the world are very vulnerable to terrorist threats in the form of large vehicle bombs. The larger bomb, the larger is the damage and its extent. The number of containers and vehicles crossing land or sea ports of entry is huge. Tough the probability is low, any vehicle may contain a threat. Any system addressing these enormous security tasks should obviously be based on excellent human intelligence to focus the attention on a much smaller number of high-risk containers and vehicles. These containers must then be subjected to a thorough and reliable inspection for the threats.Viable security system must incorporate a credible and effective inspection to achieve its purposes. It should have high performance and be operationally acceptable. This means the system must possess high detection capabilities, low false positive rate, fast response and provide automatic decision eliminating the need for human interpretation. Ancore has developed a range of new inspection devices, which are highly suitable for the above tasks. All the systems are automatic, material specific, high performance for a wide range and type of threats. Some of them are also highly modular, and compact. Some of the systems are fixed, other are relocatable, or fully mobile. The presentation will discuss Ancore's VEDS (Vehicle Explosive Detection System) which detects bulk explosives (expandable also to radiological and nuclear threats)) in marine containers, trucks and cars. The compact and rugged nature of the VEDS sensor makes it suitable for many forms of conveyance: mobile (van mounted), portal, forklift mounted, or mounted on container unloading rig. The physics principles of the system and some recent applications and results will be presented

  12. Study and discussion on management of nuclear island in-service inspection procedure system in nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Xueliang; Fan Yancheng

    2014-01-01

    In-service inspection of nuclear island is the important way for keeping safety operation of nuclear power plant. Taking Daya Bay Nuclear Power Plant as example, the management problems of in-service inspection system was studied and discussed from the angle of references, contents, classifications etc. Based on comparison with French practice, some points of view on perfection of in-service inspection system and improvement of management ability under future multi-bases and multi-units management mode were presented. (authors)

  13. Internal inspection of reinforced concrete for nuclear structures using shear wave tomography

    International Nuclear Information System (INIS)

    Scott, David B.

    2013-01-01

    Highlights: • Aging of reinforced concrete used for worldwide nuclear structures is increasing and necessitating evaluation. • Nondestructive evaluation is a tool for assessing the condition of reinforced concrete of nuclear structures. • Ultrasonic shear wave tomography as a stress wave technique has begun to be utilized for investigation of concrete material. • A study using ultrasonic shear wave tomography indicates anomalies vital to the long-term operation of the structure. • The use of this technique has shown to successfully evaluate the internal state of reinforced concrete members. - Abstract: Reinforced concrete is important for nuclear related structures. Therefore, the integrity of structural members consisting of reinforced concrete is germane to the safe operation and longevity of these facilities. Many issues that reduce the likelihood of safe operation and longevity are not visible on the surface of reinforced concrete material. Therefore, an investigation of reinforced concrete material should include techniques which will allow peering into the concrete member and determining its internal state. The performance of nondestructive evaluations is pursuant to this goal. Some of the categories of nondestructive evaluations are electrochemical, magnetism, ground penetrating radar, and ultrasonic testing. A specific ultrasonic testing technique, namely ultrasonic shear wave tomography, is used to determine presence and extent of voids, honeycombs, cracks perpendicular to the surface, and/or delamination. This technique, and others similar to it, has been utilized in the nuclear industry to determine structural conditions

  14. A Laser-based Ultrasonic Inspection System to Detect Micro Fatigue Cracks

    International Nuclear Information System (INIS)

    Park, Seung Kyu; Baik, Sung Hoon; Park, Moon Cheol; Lim, Chang Hwan; Cha, Hyung Ki

    2005-01-01

    Laser-based ultrasonic techniques have been established as a viable non-contact alternative to piezoelectric transducers for generating and receiving ultrasound. Laser-based ultrasonic inspection system provides a number of advantages over the conventional generation by piezoelectric transducers, especially a non-contact generation and detection of ultrasonic waves, high spatial scanning resolution, controllable narrow-band and wide-band spectrum, absolute measurements of the moving distance, use of fiber optics, and an ability to operate on curved and rough surfaces and at hard-to-access locations like a nuclear power plant. Ochiai and Miura used the laser-based ultrasound to detect micro fatigue cracks for the inspection of a material degradation in nuclear power plants. This widely applicable laser-based ultrasonic inspection system is comparatively expensive and provides low signal-to-noise ratio to measure ultrasound by using the laser interferometer. Many studies have been carried out to improve the measuring efficiency of the laser interferometer. One of the widely used laser interferometer types to measure the ultrasound is the Confocal Fabry-Perot Interferometer(CFPI). The measurement gain of the CFPI is slightly and continually varied according to the small change of the cavity length and the fluctuations of the measuring laser beam frequency with time. If we continually adjust the voltage of a PZT which is fixed to one of the interferometer mirrors, the optimum working point of the CFPI can be fixed. Though a static stabilizer can fix the gain of the CFPI where the CW laser beam is targeted at one position, it can not be used when the CW laser beam is scanned like a scanning laser source(SLS) technique. A dynamic stabilizer can be used for the scanning ultrasonic inspection system. A robust dynamic stabilizer is needed for an application to the industrial inspection fields. Kromine showed that the SLS technique is effective to detect small fatigue cracks

  15. Increased capability of Strassy: the decision making aid for the inspection of nuclear materials; Prolongement des capacites de Strassy: systeme d`aide a la decision pour le controle des matieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Werkoff, F [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Preston, N [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; [CRIL-Ingenierie, 92 -Puteaux (France); Le Manchec, K [CRIL-Ingenierie, 92 - Puteaux (France); Dumas, M [CEA Centre d` Etudes de Saclay, 91 - Gif-sur-Yvette (France). Direction des Reacteurs Nucleaires

    1994-12-31

    The paper describes the latest developments in STRASSY (Strategy Assistance System), the strategy assistance system for the inspection of nuclear materials. The user can now select the fuel cycle he wishes to investigate from an initial range of 19 facilities. An inspection interface has been developed to enable the details and dates of inspections to be modified. One of the special features of the application of STRASSY in international safeguards is the taking into account of timeliness of detection; certain aspects of the time manager algorithms are presented and analysed, including the guaranteed existence of a solution. The results of a study of diversion paths in a simplified cycle consisting of our facilities are presented. Finally, the modifications necessary to enable STRASSY to be used for a posterior analysis of inspection results are discussed. (authors). 7 refs., 3 figs.

  16. High Pressure Coolant Injection (HPCI) system risk-based inspection guide: Pilgrim Nuclear Power Station

    International Nuclear Information System (INIS)

    Shier, W.; Gunther, W.

    1992-10-01

    A review of the operating experience for the High Pressure Coolant Injection (HPCI) system at the Pilgrim Nuclear Power Station is described in this report. The information for this review was obtained from Pilgrim Licensee Event Reports (LERs) that were generated between 1980 and 1989. These LERs have been categorized into 23 failure modes that have been prioritized based on probabilistic risk assessment considerations. In addition, the results of the Pilgrim operating experience review have been compared with the results of of a similar, industry wide operating experience review. this comparison provides an indication of areas in the Pilgrim HPCI system that should be given increased attention in the prioritization of inspection resources

  17. Task analysis and structure scheme for center manager station in large container inspection system

    International Nuclear Information System (INIS)

    Li Zheng; Gao Wenhuan; Wang Jingjin; Kang Kejun; Chen Zhiqiang

    1997-01-01

    LCIS works as follows: the accelerator generates beam pulses which are formed into fan shape; the scanning system drags a lorry with a container passing through the beam in constant speed; the detector array detects the beam penetrating the lorry; the projection data acquisition system reads the projections and completes an inspection image of the lorry. All these works are controlled and synchronized by the center manage station. The author will describe the process of the projection data acquisition in scanning mode and the methods of real-time projection data processing. the task analysis and the structure scheme of center manager station is presented

  18. Optimum power of radiation dose in X ray television systems of flaw inspection in industry

    International Nuclear Information System (INIS)

    Denbnovetskii, S.V.; Troitskii, V.A.; Belyi, N.G.; Grom, V.S.; Kuz'micheva, N.V.; Leshchishin, A.V.; Mikhailov, V.N.; Shutenko, O.V.

    1990-01-01

    The authors present the experimental dose characteristics of a x ray television system based on x ray vidicons with the diameter of the working field of 900 mm which operate in the continuous and pulsed conditions with the longer time of cumulation of radiation images on the target of the x ray vidicon. For each type of the inspected material, its thickness, and cumulation time, the dose characteristics were used to determine the optimum power of the exposure dose ensuring the maximum signal/noise ratio and detectability of the defects at the output of the system. (author)

  19. Adequacy Criteria of Models of the Cargo Inspection System with Material Discrimination Option

    International Nuclear Information System (INIS)

    Osipov, S; Chakhlov, S; Osipov, O; Shtein, A; Van, J

    2016-01-01

    Generalized adequacy criteria for mathematical models in order to discriminate materials in X-ray inspection systems by the dual-energy method were developed. Two main approaches of the examination systems to produce the adequacy criteria by the final and the intermediate parameters of the dual-energy method were analyzed. The criteria were specified in respect to the discrimination by the effective atomic number and by the method of level functions. Experimental and theoretical estimates of the discrimination parameters of the test object constituents scanned by fan beams of X-ray radiation with the maximal energies of 4.5 and 9 MeV are given. (paper)

  20. Performance of a tagged neutron inspection system (TNIS) based on portable sealed generators

    International Nuclear Information System (INIS)

    Nebbia, G.; Pesente, S.; Lunardon, M.; Viesti, G.; LeTourneur, P.; Heuveline, F.; Mangeard, M.; Tcheng, C.

    2004-01-01

    A portable sealed neutron generator has been modified to produce 14MeV tagged neutron beams with an embedded YAP:Ce scintillation detector. The system has been tested by detecting the coincident gamma-rays produced in the irradiation of a graphite sample by means of a standard NaI(Tl) scintillator. Time resolution of about δt=4-5ns (FWHM) has been measured. The sealed neutron tube has been operated up to 10 7 neutron/s. Possible applications in non-destructive assays and future developments of the Tagged Neutron Inspection System concept are discussed

  1. Underwater inspection and maintenance programs within nuclear and non-nuclear related operating systems

    International Nuclear Information System (INIS)

    Vallance, C.; Goulet, B.; Black, S.

    2008-01-01

    The increasing age of the nuclear and non-nuclear power generating facilities requires extended inspection, repair and maintenance (IRM) activities to prolong the operation of these facilities past their original design life. Commercial divers are often utilized to perform critical work at nuclear power plants, fuel reprocessing plants, waste storage facilities, and research institutions. These various tasks include inspection, welding, mechanical modifications and repairs, coating applications, and work associated with plant decommissioning. Programs may take place in areas such as the reactor vessel, equipment pool, spent fuel pool, and suppression chamber using manned intervention and remotely operated vehicles. Some of these tasks can also be conducted using remotely operated vehicles (ROV's). Although specialist robots are not uncommon to the nuclear industry, the use of free-swimming vehicle's and remote systems for the inspection of underwater assets has increased due to improvements of the supporting technologies and information requirements needed to extend the life of these facilities. This paper will provide an overview of the procedures and equipment necessary to perform unique work tasks using manned and unmanned techniques. (author)

  2. Machine vision system: a tool for quality inspection of food and agricultural products.

    Science.gov (United States)

    Patel, Krishna Kumar; Kar, A; Jha, S N; Khan, M A

    2012-04-01

    Quality inspection of food and agricultural produce are difficult and labor intensive. Simultaneously, with increased expectations for food products of high quality and safety standards, the need for accurate, fast and objective quality determination of these characteristics in food products continues to grow. However, these operations generally in India are manual which is costly as well as unreliable because human decision in identifying quality factors such as appearance, flavor, nutrient, texture, etc., is inconsistent, subjective and slow. Machine vision provides one alternative for an automated, non-destructive and cost-effective technique to accomplish these requirements. This inspection approach based on image analysis and processing has found a variety of different applications in the food industry. Considerable research has highlighted its potential for the inspection and grading of fruits and vegetables, grain quality and characteristic examination and quality evaluation of other food products like bakery products, pizza, cheese, and noodles etc. The objective of this paper is to provide in depth introduction of machine vision system, its components and recent work reported on food and agricultural produce.

  3. SIIA: a knowledge-based assistant for the SAFT ultrasonic inspection system(a)

    International Nuclear Information System (INIS)

    Melton, R.B.; Doctor, S.R.; Taylor, T.T.; Badalamente, R.V.

    1987-01-01

    SIIA(b) is a knowledge-based system designed to assist in making the operation of the Synthetic Aperture Focussing Technique (SAFT) Ultrasonic Inspection System more reliable and efficient. This paper reports on their effort to develop a prototype version of SIIA to demonstrate the feasibility of using knowledge-based systems in nondestructive evaluation (NDE). The first section of the paper describes the structure of the problem and their conceptual design of the knowledge-based system. The next section describes the current state of the prototype SIIA system and relates some of their experiences in developing the system. The final section discusses their plans for future development of SIIA and the implications of this type of system for other NDE techniques and applications

  4. An extended optimal replacement model for a deteriorating system with inspections

    International Nuclear Information System (INIS)

    Sheu, Shey-Huei; Tsai, Hsin-Nan; Wang, Fu-Kwun; Zhang, Zhe George

    2015-01-01

    This study considers a generalized replacement model for a deteriorating system in which failures can only be detected by inspection. The system is assumed to have two types of failures and is replaced at the occurrence of the Nth type I failure (minor failure), or the first type II failure (catastrophic failure), or at working age T, whichever occurs first. The probability of a type I or type II failure depends on the number of type I failures since the previous replacement. Such a system can be repaired after a type I failure, but is deteriorating stochastically. That is, the operating intervals are decreasing stochastically, whereas the durations of the repairs are increasing stochastically. Based on these assumptions, we determine the expected net cost rate and discuss various special cases of the model. Finally, we develop a computational algorithm for finding the optimal policy and present a numerical example to show the properties of the proposed model. - Highlight: • Replacement policy for system subject two types of failures or the system's working age. • Failures detected by inspections. • Decreasing operating times and increasing repair times. • Derive a cost function. • Determine the cost minimization policy

  5. Vision-Based Target Finding and Inspection of a Ground Target Using a Multirotor UAV System.

    Science.gov (United States)

    Hinas, Ajmal; Roberts, Jonathan M; Gonzalez, Felipe

    2017-12-17

    In this paper, a system that uses an algorithm for target detection and navigation and a multirotor Unmanned Aerial Vehicle (UAV) for finding a ground target and inspecting it closely is presented. The system can also be used for accurate and safe delivery of payloads or spot spraying applications in site-specific crop management. A downward-looking camera attached to a multirotor is used to find the target on the ground. The UAV descends to the target and hovers above the target for a few seconds to inspect the target. A high-level decision algorithm based on an OODA (observe, orient, decide, and act) loop was developed as a solution to address the problem. Navigation of the UAV was achieved by continuously sending local position messages to the autopilot via Mavros. The proposed system performed hovering above the target in three different stages: locate, descend, and hover. The system was tested in multiple trials, in simulations and outdoor tests, from heights of 10 m to 40 m. Results show that the system is highly reliable and robust to sensor errors, drift, and external disturbance.

  6. Development of Inspection Data Collection and Evaluation System (IDES) for J-MOX (1)

    International Nuclear Information System (INIS)

    Kumakura, Shinichi; Takizawa, Koji; Masuda, Shoichiro; Iso, Shoko; Kikuchi, Masahiro; Hisamatsu, Yoshinori; Kurobe, Hiroko; Kawasue, Akane

    2012-01-01

    'Inspection Data and Collection and Evaluation System' is the system to storage inspection data and operator declaration data collected from various measurement equipments, which are installed in fuel fabrication processes of the large-scale MOX fuel fabrication plant, and to make safeguards evaluation using these data. Nuclear Material Control Center is now developing this system under the project commissioned by JSGO. By last fiscal year, we developed the simulator to simulate fuel fabrication process and generate data simulating in-process material inventory/flow and these measurement data. In addition, we developed a verification evaluation system to calculate various statistics from the simulation data and conduct statistical tests such as NRTA in order to verify the adequacy of material accountancy for the fabrication process. We are currently investigating the adequacy of evaluation itself and effects for evaluation by changing various process factors including unmeasured inventories as well as the adequacy of current safeguards approach. In the presentation, we explain the developed system configuration, calculation method of the simulation etc. and demonstrate same examples of the simulated result on material flow in the fabrication process and a part of the analytical results. (author)

  7. The Mechatronic System Design Of Ultrasonic Scanner For Inservice Inspection Of Research Reactor

    Science.gov (United States)

    Handono, Khairul; Kristedjo, K.; Awwaluddin, M.; Shobary, Ihsan

    2018-02-01

    The mechatronic system design of ultrasonic scanner for inservices inspection of Research Reactor has been conducted. The requirement designed must be reliable operated, safety to personnel and equipments, ease of maintenance and operation, protection of equipment mechanically, interchangeability of equipments and addition of the several model of probe immersion ultrasonic tranducer. In order to achieve the above goals and obtain the desired results, a mechatronic design based on mechanical and electronic practical experiences will be needed. In this paper consist of the mechanical design and the system mechanical movement using stepper motor control. The criteria and the methods of designs of mechanical and electronic equipments of the system have been discussed and investigated. A mechanical and instrumentation control system drawing and requirement of design will be presented as the outcome of the design. The designed of mechanical system is consequently simulated by solidwork software. The intention of the above research is to create solutions in different ways of inservice inspection of integrity of Reactor.

  8. NRF Based Nondestructive Inspection System for SNM by Using Laser-Compton-Backscattering Gamma-Rays

    Science.gov (United States)

    Ohgaki, H.; Omer, M.; Negm, H.; Daito, I.; Zen, H.; Kii, T.; Masuda, K.; Hori, T.; Hajima, R.; Hayakawa, T.; Shizuma, T.; Kando, M.

    2015-10-01

    A non-destructive inspection system for special nuclear materials (SNMs) hidden in a sea cargo has been developed. The system consists of a fast screening system using neutron generated by inertial electrostatic confinement (IEC) device and an isotope identification system using nuclear resonance fluorescence (NRF) measurements with laser Compton backscattering (LCS) gamma-rays has been developed. The neutron flux of 108 n/sec has been achieved by the IEC in static mode. We have developed a modified neutron reactor noise analysis method to detect fission neutron in a short time. The LCS gamma-rays has been generated by using a small racetrack microtoron accelerator and an intense sub-nano second laser colliding head-on to the electron beam. The gamma-ray flux has been achieved more than 105 photons/s. The NRF gamma-rays will be measured using LaBr3(Ce) scintillation detector array whose performance has been measured by NRF experiment of U-235 in HIGS facility. The whole inspection system has been designed to satisfy a demand from the sea port.

  9. The development of robotic system for inspecting and repairing NPP primary coolant system of high-level radioactive environment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Kim, Ki Ho; Jung, Seung Ho; Kim, Byung Soo; Hwang, Suk Yeoung; Kim, Chang Hoi; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Cho, Jai Wan; Lee, Jae Kyung; Lee, Yong Deok

    1997-07-01

    This project aims at developing a robotic system to automatically handle inspection and maintenance of NPP safety-related facilities in high-level radioactive environment. This robotic system under development comprises two robots depending on application fields - a mobile robot and multi-functional robot. The mobile robot is designed to be used in the area of primary coolant system during the operation of NPP. This robot enables to overcome obstacles and perform specified tasks in unstructured environment. The multi-functional robot is designed for performing inspection and maintenance tasks of steam generator and nuclear reactor vessel during the overhaul periods of NPP. Nuclear facilities can be inspected and repaired all the time by use of both the mobile robot and the multi-functional robot. Human operator, by teleoperation, monitors the movements of such robots located at remote task environment via video cameras and controls those remotely generating desired commands via master manipulator. We summarize the technology relating to the application of the mobile robot to primary coolant system environment, the applicability of the mobile robot through 3D graphic simulation, the design of the mobile robot, the design of its radiation-hardened controller. We also describe the mechanical design, modeling, and control system of the multi-functional robot. Finally, we present the design of the force-reflecting master and the modeling of virtual task environment for a training simulator. (author). 47 refs., 16 tabs., 43 figs.

  10. The development of robotic system for inspecting and repairing NPP primary coolant system of high-level radioactive environment

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Kim, Ki Ho; Jung, Seung Ho; Kim, Byung Soo; Hwang, Suk Yeoung; Kim, Chang Hoi; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Cho, Jai Wan; Lee, Jae Kyung; Lee, Yong Deok.

    1997-07-01

    This project aims at developing a robotic system to automatically handle inspection and maintenance of NPP safety-related facilities in high-level radioactive environment. This robotic system under development comprises two robots depending on application fields - a mobile robot and multi-functional robot. The mobile robot is designed to be used in the area of primary coolant system during the operation of NPP. This robot enables to overcome obstacles and perform specified tasks in unstructured environment. The multi-functional robot is designed for performing inspection and maintenance tasks of steam generator and nuclear reactor vessel during the overhaul periods of NPP. Nuclear facilities can be inspected and repaired all the time by use of both the mobile robot and the multi-functional robot. Human operator, by teleoperation, monitors the movements of such robots located at remote task environment via video cameras and controls those remotely generating desired commands via master manipulator. We summarize the technology relating to the application of the mobile robot to primary coolant system environment, the applicability of the mobile robot through 3D graphic simulation, the design of the mobile robot, the design of its radiation-hardened controller. We also describe the mechanical design, modeling, and control system of the multi-functional robot. Finally, we present the design of the force-reflecting master and the modeling of virtual task environment for a training simulator. (author). 47 refs., 16 tabs., 43 figs

  11. Putting Automated Visual Inspection Systems To Work On The Factory Floor: What's Missing?

    Science.gov (United States)

    Waltz, Frederick M.; Snyder, Michael A.; Batchelor, Bruce G.

    1990-02-01

    Machine vision systems and other automated visual inspection (AVI) systems have been proving their usefulness in factories for more than a decade. In spite of this, the number of installed systems is far below the number that could profitably be employed. In the opinion of the authors, the primary reason for this is the high cost of customizing vision systems to meet applications requirements. A three-part approach to this problem has proven to be useful: 1. A multi-phase paradigm for customer interaction, system specification, system development, and system installation; 2. A powerful and easy-to-use system development environment, including a a flexible laboratory lighting setup, plus software-based tools to assist in the design of image acquisition systems, b. an image processing environment with a very large repertoire of image processing and feature extraction operations and an easy-to-use command interpreter having macro capabilities, and c. an image analysis environment with high-level constructs, a flexible and powerful syntax, and a "seamless" interface to the image processing level; and 3. A moderately-priced high-speed "target" system fully compatible with the development environment, so that algorithms developed thereon can be transferred directly to the factory environment without further development costs or reprogramming. Items 1 and 2 are covered in other papers1,23,4,5 and are touched on here only briefly. Item 3 is the main subject of this paper. Our major motivation in presenting this paper is to offer suggestions to vendors developing commercial boards and systems, in hopes that the special needs of industrial inspection can be met.

  12. Inspection of float glass using a novel retroreflective laser scanning system

    Science.gov (United States)

    Holmes, Jonathan D.

    1997-07-01

    Since 1988, Image Automation has marketed a float glass inspection system using a novel retro-reflective laser scanning system. The (patented) instrument scans a laser beam by use of a polygon through the glass onto a retro-reflective screen, and collects the retro-reflected light off the polygon, such that a stationary image of the moving spot on the screen is produced. The spot image is then analyzed for optical effects introduced by defects within the glass, which typically distort and attenuate the scanned laser beam, by use of suitable detectors. The inspection system processing provides output of defect size, shape and severity, to the factory network for use in rejection or sorting of glass plates to the end customer. This paper briefly describes the principles of operation, the system architecture, and limitations to sensitivity and measurement repeatability. New instruments based on the retro-reflective scanning method have recently been developed. The principles and implementation are described. They include: (1) Simultaneous detection of defects within the glass and defects in a mirror coating on the glass surface using polarized light. (2) A novel distortion detector for very dark glass. (3) Measurement of optical quality (flatness/refractive homogeneity) of the glass using a position sensitive detector.

  13. Design of an Infrared Imaging System for Robotic Inspection of Gas Leaks in Industrial Environments

    Directory of Open Access Journals (Sweden)

    Ramon Barber

    2015-03-01

    Full Text Available Gas detection can become a critical task in dangerous environments that involve hazardous or contaminant gases, and the use of imaging sensors provides an important tool for leakage location. This paper presents a new design for remote sensing of gas leaks based on infrared (IR imaging techniques. The inspection system uses an uncooled microbolometer detector, operating over a wide spectral bandwidth, that features both low size and low power consumption. This equipment is boarded on a robotic platform, so that wide objects or areas can be scanned. The detection principle is based on the use of active imaging techniques, where the use of external IR illumination enhances the detection limit and allows the proposed system to operate in most cases independently from environmental conditions, unlike passive commercial approaches. To illustrate this concept, a fully radiometric description of the detection problem has been developed; CO2 detection has been demonstrated; and simulations of typical gas detection scenarios have been performed, showing that typical industrial leaks of CH4 are well within the detection limits. The mobile platform where the gas sensing system is going to be implemented is a robot called TurtleBot. The control of the mobile base and of the inspection device is integrated in ROS architecture. The exploration system is based on the technique of Simultaneous Localization and Mapping (SLAM that makes it possible to locate the gas leak in the map.

  14. NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

    International Nuclear Information System (INIS)

    Chang, Choong Koo; Kim, Young Joo

    2013-01-01

    Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system

  15. NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Choong Koo; Kim, Young Joo [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system.

  16. Conceptual design of an in-vessel inspection robotic system for Tokamak environment

    International Nuclear Information System (INIS)

    Kumar, Prabhat; Raju, Daniel; Ranjan, Vaibhav; Patel, Prateek; Dave, Jatinkumar; Naik, Mehul

    2013-01-01

    An in-vessel inspection robotic system has been conceptualized for operation inside a tokamak vessel. The robotic system is envisaged to comprise of a robotic arm, end-effector, microcontroller and wireless communication system. The end-effector is envisaged to be a special purpose camera for in-situ inspection between plasma shots. The three-link robotic arm, designed for ITER-like environment, has 4 revolute joints- 3 providing manipulation in poloidal plane and the fourth one providing limited movement in adjacent toroidal planes. This paper provides the conceptual design of the system along with kinematic analysis of robotic arm. Solutions have been derived for forward and inverse kinematic models and the Jacobian matrix for the robotic arm linkage. In forward kinematic model, given a set of joint-link parameters, the position and orientation of end-effector are determined with respect to a reference frame. In inverse kinematic model, given the specified position and orientation of end-effector with respect to a reference frame, a set of joint variables are derived that would bring the end-effector into the required posture. Using Jacobian matrix, the relation between the end-effector velocity and the joint velocity of a manipulator is obtained i.e. given the individual joint velocity; the end-effector velocity is obtained. A CAD model has been generated using CATIA to simulate the kinematic model and carry out computational stress analysis. (author)

  17. High-speed potato grading and quality inspection based on a color vision system

    Science.gov (United States)

    Noordam, Jacco C.; Otten, Gerwoud W.; Timmermans, Toine J. M.; van Zwol, Bauke H.

    2000-03-01

    A high-speed machine vision system for the quality inspection and grading of potatoes has been developed. The vision system grades potatoes on size, shape and external defects such as greening, mechanical damages, rhizoctonia, silver scab, common scab, cracks and growth cracks. A 3-CCD line-scan camera inspects the potatoes in flight as they pass under the camera. The use of mirrors to obtain a 360-degree view of the potato and the lack of product holders guarantee a full view of the potato. To achieve the required capacity of 12 tons/hour, 11 SHARC Digital Signal Processors perform the image processing and classification tasks. The total capacity of the system is about 50 potatoes/sec. The color segmentation procedure uses Linear Discriminant Analysis (LDA) in combination with a Mahalanobis distance classifier to classify the pixels. The procedure for the detection of misshapen potatoes uses a Fourier based shape classification technique. Features such as area, eccentricity and central moments are used to discriminate between similar colored defects. Experiments with red and yellow skin-colored potatoes have shown that the system is robust and consistent in its classification.

  18. Development of a NDI system using the magneto-optical method. 2. Remote sensing using the novel magneto-optical inspection system

    International Nuclear Information System (INIS)

    Lee, Jinyi; Shoji, Tetsuo

    1999-01-01

    A new remote sensing system using the magneto-optical method is developed for inspection of flaws introduced during service operation where routine inspection is difficult because of difficult inaccessibility to the components. Among the advantages of non-destructive inspection (NDI) based on the magneto-optical sensor are: real time inspection, elimination of electrical noise and high spatial resolution. Remote sensing of flaws is achieved using the basic principles of Faraday effect, optical permeability, and diffraction of a laser by the domain walls. This paper describes a novel remote NDI system using the principles of optics and LMF. The main characteristic of the system is that image data and LMF information can be obtained simultaneously. It is possible to carry out remote and high speed inspection of cracks from the intensity of reflected light, and to estimate the size of a crack effectively with their diverse data. The advantages of this NDI system are demonstrated using two specimens. (author)

  19. A Novel Machine Vision System for the Inspection of Micro-Spray Nozzle

    Directory of Open Access Journals (Sweden)

    Kuo-Yi Huang

    2015-06-01

    Full Text Available In this study, we present an application of neural network and image processing techniques for detecting the defects of an internal micro-spray nozzle. The defect regions were segmented by Canny edge detection, a randomized algorithm for detecting circles and a circle inspection (CI algorithm. The gray level co-occurrence matrix (GLCM was further used to evaluate the texture features of the segmented region. These texture features (contrast, entropy, energy, color features (mean and variance of gray level and geometric features (distance variance, mean diameter and diameter ratio were used in the classification procedures. A back-propagation neural network classifier was employed to detect the defects of micro-spray nozzles. The methodology presented herein effectively works for detecting micro-spray nozzle defects to an accuracy of 90.71%.

  20. A portable inspection system to estimate direct glare of various LED modules

    Science.gov (United States)

    Chen, Po-Li; Liao, Chun-Hsiang; Li, Hung-Chung; Jou, Shyh-Jye; Chen, Han-Ting; Lin, Yu-Hsin; Tang, Yu-Hsiang; Peng, Wei-Jei; Kuo, Hui-Jean; Sun, Pei-Li; Lee, Tsung-Xian

    2015-07-01

    Glare is caused by both direct and indirect light sources and discomfort glare produces visual discomfort, annoyance, or loss in visual performance and visibility. Direct glare is caused by light sources in the field of view whereas reflected glare is caused by bright reflections from polished or glossy surfaces that are reflected toward an individual. To improve visual comfort of our living environment, a portable inspection system to estimate direct glare of various commercial LED modules with the range of color temperature from 3100 K to 5300 K was developed in this study. The system utilized HDR images to obtain the illumination distribution of LED modules and was first calibrated for brightness and chromaticity and corrected with flat field, dark-corner and curvature by the installed algorithm. The index of direct glare was then automatically estimated after image capturing, and the operator can recognize the performance of LED modules and the possible effects on human being once the index was out of expecting range. In the future, we expect that the quick-response smart inspection system can be applied in several new fields and market, such as home energy diagnostics, environmental lighting and UGR monitoring and popularize it in several new fields.

  1. A real-time 3D scanning system for pavement distortion inspection

    International Nuclear Information System (INIS)

    Li, Qingguang; Yao, Ming; Yao, Xun; Xu, Bugao

    2010-01-01

    Pavement distortions, such as rutting and shoving, are the common pavement distress problems that need to be inspected and repaired in a timely manner to ensure ride quality and traffic safety. This paper introduces a real-time, low-cost inspection system devoted to detecting these distress features using high-speed 3D transverse scanning techniques. The detection principle is the dynamic generation and characterization of the 3D pavement profile based on structured light triangulation. To improve the accuracy of the system, a multi-view coplanar scheme is employed in the calibration procedure so that more feature points can be used and distributed across the field of view of the camera. A sub-pixel line extraction method is applied for the laser stripe location, which includes filtering, edge detection and spline interpolation. The pavement transverse profile is then generated from the laser stripe curve and approximated by line segments. The second-order derivatives of the segment endpoints are used to identify the feature points of possible distortions. The system can output the real-time measurements and 3D visualization of rutting and shoving distress in a scanned pavement

  2. A low-cost, modular, microwave-linked, color TV inspection system

    International Nuclear Information System (INIS)

    Panda, N.C.

    1991-01-01

    This paper reports that many custom-built radiation-shielded CCTV inspection systems for nuclear facilities are available in the market. This author, however, could find no reference to units using low-cost nodular technology for wireless transmission and control of color CCTV signals in radiation environments. The system that was developed is a process control observation tool geared toward identifying locations ad volumes of accumulated in-cell solids. It also performs remote integrity assessments of tanks and pipe routings that are required by regulatory agencies. System highlights are: microwave transmission of video and control signals, low cost, low maintenance, and modular design. Use of standard components enables easy exchange of modules. Microwave transmission resolved the complications of a wired system while increasing reliability and safety. The video image is created by the remote in-cell color TV camera and transmitted by microwave out of the cell to TV monitors at consoles in non-radiation zones

  3. Design and development of Pc-based TOFD ultrasonic scanning system for welds inspection

    International Nuclear Information System (INIS)

    Suhairy Sani; Mohamad Pauzi Ismai; Muhammad Faiz Mohd Shukri; Amry Amin Abas

    2010-01-01

    This paper describes the design and development of a portable PC-based ultrasonic scanning system for industrial applications. The system which is called TOFD Ultrasonic Scanning System (TOFUSS) is used to create a gray scale imaging techniques are applied to the RF (AC) signal phase and enables weld integrity to be observed in real time. TOFD consists of a separate ultrasonic transmitter and receiver. The Probes are aimed at the same point in the weld volume. The entire weld is flooded with ultrasound allowing inspection of the weld. With a time of flight path, the ultrasonic velocity and the spatial relationship of the two probes, location and height of the defects can be very accurately calculated. The algorithm and complete system were implemented in a computer software developed using Microsoft Visual BASIC 6.0. (author)

  4. 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.)

  5. Development of In-Service Inspection system for heat transfer tubes in the primary pressurized water cooler in the HTTR

    Energy Technology Data Exchange (ETDEWEB)

    Shinozaki, Masayuki; Furusawa, Takayuki [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Wada, Shigeyuki

    1999-08-01

    The ISI (In-Service Inspection) system has been developed so as to maintain the structural integrity of heat transfer tubes in the primary pressurized water cooler in the HTTR (High Temperature Engineering Test Reactor). This system consists of eddy current probes, ultra-sonic probes, insertion and extraction units, positioning unit and so on. Verification and performance tests of the developed ISI system were carried out using mock-up heat transfer tubes in the primary pressurized water cooler. The constitution of the system, R and D results of the inspection probes, and verification and performance test results of the ISI system for heat transfer tubes are described in this paper. (author)

  6. Facilitating Automation Development in Internal Logistics Systems

    OpenAIRE

    Granlund, Anna

    2014-01-01

    The internal logistics system includes all activities connected with managing the flow of materials within the physical limits of a facility. This system is an important part of operations in need of increased focus and continuous improvements. Automation is one possible tool with a previously confirmed great potential to improve internal logistics. Despite this great potential and a growing trend of using automation in the area, internal logistics activities are still not automated to the sa...

  7. African Health Systems Initiative (AHSI) | IDRC - International ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    The African Health Systems Initiative (AHSI) is a 10-year Canadian International ... for strengthening African-led health systems and human resources for health. ... IDRC congratulates first cohort of Women in Climate Change Science Fellows.

  8. Radiological risks from irradiation of cargo contents with EURITRACK neutron inspection systems

    International Nuclear Information System (INIS)

    Giroletti, E.; Bonomi, G.; Donzella, A.; Viesti, G.; Zenoni, A.

    2012-01-01

    The radiological risk for the population related to the neutron irradiation of cargo containers with a tagged neutron inspection system has been studied. Two possible effects on the public health have been assessed: the modification of the nutritional and organoleptic properties of the irradiated materials, in particular foodstuff, and the neutron activation of consumer products (i.e. food and pharmaceuticals). The result of this study is that irradiation of food and foodstuff, pharmaceutical and medical devices in container cargoes would neither modify the properties of the irradiated material nor produce effective doses of concern for public health. Furthermore, the dose received by possible stowaways present inside the container during the inspection is less than the annual effective dose limit defined by European Legislation for the public. - Highlights: ► Neutron irradiation of cargo containers implies a radiological risk. ► The risk is about the modification of food properties and the products activation. ► Assessment is made about the EURITRACK neutron irradiation system. ► Results show that the EURITRACK scanning is not dangerous for the population.

  9. A Mobile Robotic System for the Inspection and Repair of SG Tubes in NPPs

    Directory of Open Access Journals (Sweden)

    Yong-Chil Seo

    2016-04-01

    Full Text Available The reliability and performance of a steam generator (SG is one of the serious concerns in the operation of pressurized water nuclear power plants. Because of high levels of radiation, robotic systems have been used to inspect and repair SG tubes. In this paper, we present a mobile robotic system that positions the inspection and repair tools while hanging down from the tube sheets where the tubes are fixed. All of the driving mechanisms of the mobile robot are actuated by electric motors to start its works, providing that the electric power is prepared without the additional need for an on-site air services. A special tube-holding mechanism with a high holding force has been developed to prevent falling from the tube sheets, even in the case of an electric power failure. We have also developed a quick installation guide device that guides the mobile robot to desired initial positions in the tube sheet exactly and quickly, which helps to reduce the radiation exposure of human workers during the installation work. This paper also provides on-site experimental results and lessons learned.

  10. Development of automatic radiographic inspection system using digital image processing and artificial intelligence

    International Nuclear Information System (INIS)

    Itoga, Kouyu; Sugimoto, Koji; Michiba, Koji; Kato, Yuhei; Sugita, Yuji; Onda, Katsuhiro.

    1991-01-01

    The application of computers to welding inspection is expanding rapidly. The classification of the application is the collection, analysis and processing of data, the graphic display of results, the distinction of the kinds of defects and the evaluation of the harmufulness of defects and the judgement of acceptance or rejection. The application of computer techniques to the automation of data collection was realized at the relatively early stage. Data processing and the graphic display of results are the techniques in progress now, and the application of artificial intelligence to the distinction of the kinds of defects and the evaluation of harmfulness is expected to expand rapidly. In order to computerize radiographic inspection, the abilities of image processing technology and knowledge engineering must be given to computers. The object of this system is the butt joints by arc welding of the steel materials of up to 30 mm thickness. The digitizing transformation of radiographs, the distinction and evaluation of transmissivity and gradation by image processing, and only as for those, of which the picture quality satisfies the standard, the extraction of defect images, their display, the distinction of the kinds and the final judgement are carried out. The techniques of image processing, the knowledge for distinguishing the kinds of defects and the concept of the practical system are reported. (K.I.)

  11. Real-time distortion correction for visual inspection systems based on FPGA

    Science.gov (United States)

    Liang, Danhua; Zhang, Zhaoxia; Chen, Xiaodong; Yu, Daoyin

    2008-03-01

    Visual inspection is a kind of new technology based on the research of computer vision, which focuses on the measurement of the object's geometry and location. It can be widely used in online measurement, and other real-time measurement process. Because of the defects of the traditional visual inspection, a new visual detection mode -all-digital intelligent acquisition and transmission is presented. The image processing, including filtering, image compression, binarization, edge detection and distortion correction, can be completed in the programmable devices -FPGA. As the wide-field angle lens is adopted in the system, the output images have serious distortion. Limited by the calculating speed of computer, software can only correct the distortion of static images but not the distortion of dynamic images. To reach the real-time need, we design a distortion correction system based on FPGA. The method of hardware distortion correction is that the spatial correction data are calculated first under software circumstance, then converted into the address of hardware storage and stored in the hardware look-up table, through which data can be read out to correct gray level. The major benefit using FPGA is that the same circuit can be used for other circularly symmetric wide-angle lenses without being modified.

  12. Long-Range Untethered Real-Time Live Gas Main Robotic Inspection System

    Energy Technology Data Exchange (ETDEWEB)

    Hagen Schempf; Daphne D' Zurko

    2004-10-31

    Under funding from the Department of Energy (DOE) and the Northeast Gas Association (NGA), Carnegie Mellon University (CMU) developed an untethered, wireless remote controlled inspection robot dubbed Explorer. The project entailed the design and prototyping of a wireless self-powered video-inspection robot capable of accessing live 6- and 8-inch diameter cast-iron and steel mains, while traversing turns and Ts and elbows under real-time control with live video feedback to an operator. The design is that of a segmented actively articulated and wheel-leg powered robot design, with fisheye imaging capability and self-powered battery storage and wireless real-time communication link. The prototype was functionally tested in an above ground pipe-network, in order to debug all mechanical, electrical and software subsystems, and develop the necessary deployment and retrieval, as well as obstacle-handling scripts. A pressurized natural gas test-section was used to certify it for operation in natural gas at up to 60 psig. Two subsequent live-main field-trials in both cast-iron and steel pipe, demonstrated its ability to be safely launched, operated and retrieved under real-world conditions. The system's ability to safely and repeatably exidrecover from angled and vertical launchers, traverse multi-thousand foot long pipe-sections, make T and varied-angle elbow-turns while wirelessly sending live video and handling command and control messages, was clearly demonstrated. Video-inspection was clearly shown to be a viable tool to understand the state of this critical buried infrastructure, irrespective of low- (cast-iron) or high-pressure (steel) conditions. This report covers the different aspects of specifications, requirements, design, prototyping, integration and testing and field-trialing of the Explorer platform.

  13. Signal sensing of the internal ducts inspection robot: GIRINO (Get Inside Robot to Impel Normal Operation); Sensoriamento de sinais do robo de inspecao interna de dutos: GIRINO (Gabarito Interno Robotizado de Incidencia Normal ao Oleoduto)

    Energy Technology Data Exchange (ETDEWEB)

    Panta, Pedro G.; Dutra, Max S. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE); Santos, Auderi V.; Ferreira, Rodrigo C. [Pontificia Univ. Catolica do Rio de Janeiro (PUC-Rio), RJ (Brazil). Centro de Estudos em Telecomunicacoes; Reis, Ney S. [PETROBRAS, Rio de Janeiro, RJ (Brazil). Centro de Pesquisas

    2004-07-01

    One of the major challenges in the operation field of subway oil pipelines is the presence of blockades caused by paraffin and hydrates accumulation. The maintenance and inspection inside pipelines practiced until now imply complicated risky processes for people and equipment involved in daily operational activities. The Get Inside Robot to Impel Normal Operation (G.I.R.I.N.O.) is a robot developed by the Robotic Laboratory of PETROBRAS Research Center, that aims at looking for less risky ways in internal inspection process of pipelines which displacement movements are generated by hydraulic energy. In order to get the inspection and displacement functions, the G.I.R.I.N.O. needs a constant internal movement monitoring that is made by its several parts; the interaction with the environment in diverse processes. This paper has the objective of proposing a monitoring system for the 14 inch duct G.I.R.I.N.O. For this end, a study of available components for receiving , signal processing and visualization used in the industry that fulfill the basic requirements of the robot's performance was done. The choice of the proposed devices considers these main features: size, power consumption and marinization capability. (author)

  14. [PICS: pharmaceutical inspection cooperation scheme].

    Science.gov (United States)

    Morénas, J

    2009-01-01

    The pharmaceutical inspection cooperation scheme (PICS) is a structure containing 34 participating authorities located worldwide (October 2008). It has been created in 1995 on the basis of the pharmaceutical inspection convention (PIC) settled by the European free trade association (EFTA) in1970. This scheme has different goals as to be an international recognised body in the field of good manufacturing practices (GMP), for training inspectors (by the way of an annual seminar and experts circles related notably to active pharmaceutical ingredients [API], quality risk management, computerized systems, useful for the writing of inspection's aide-memoires). PICS is also leading to high standards for GMP inspectorates (through regular crossed audits) and being a room for exchanges on technical matters between inspectors but also between inspectors and pharmaceutical industry.

  15. Internal inspection devices

    International Nuclear Information System (INIS)

    1982-01-01

    In order to evaluate the possibilities and limits of using specific endoscopes, the design and performance of rigid and flexible endoscopes are studied. The results show on the one hand the physical conditions setting a limit to the applicability of a certain device, and on the other indicate possible ways of improving and modifying given devices so as to adapt them to the special requirements of current testing standards. Based on theoretical and practical experience, proposals for improvements are made. For rigid endoscopes, e.g., additional equipment has been developed and is described in detail, allowing hitherto existing problems to be solved, thus enlarging the range of employment and enhancing and improving the information to be gained by testing using endoscopes. (orig./RW) [de

  16. Visual inspection system and sipping design for spent fuel at TRIGA MARK III reactor of Mexico

    International Nuclear Information System (INIS)

    Delfin, A.; Mazon, R.

    2002-01-01

    In the framework of the Technical Cooperation Regional Project for Latin America RLA/4/018 for the biennium 2001-2002, one of the activities identified is the characterization of spent fuel. Of these activities an important one is not doubt the physical condition of spent fuel because an appropriate identification of the fuel status will prevent problems of fuel leaks, corrosion problems etc. As part of the activities of the project was decided that countries no having visual inspection and sipping systems should be very desirable to have them as a result of this project. The Triga reactor of Mexico does not have both of them, therefore, it was decided the need of having both system. The paper describe first the way we designed and constructed a remote Visual Inspection System and example of how is operated. Along the experience and problems we have had with the system. Also we will present the design of the Sipping system were two option were considered. First to take a sample of water after a convenient period of time passing through a circuit to a multichannel analyzer and to identify leakage by way of measuring Caesium-137. Second, exists the possibility that the Stainless Steel sleeve of the fuel has only very small failures, so it is going to be very difficult to have leakages unless the fuel is hot. Therefore we are evaluating the possibility of using heaters to increase the temperature of the fuel and succeed on detecting leakages. The results - we hope - will be ready to be presented at the meeting. (author)

  17. Optimization of thermal waste treatment with the INSPECT system by camera based characteristic values and Fuzzy Control; Optimierung der thermischen Abfallbehandlung mit dem INSPECT-System durch kamerabasierte Kenngroessen und Fuzzy Control

    Energy Technology Data Exchange (ETDEWEB)

    Keller, H.B.; Matthes, J. [Forschungszentrum Karlsruhe GmbH, Eggenstein-Leopoldshafen (Germany). Inst. fuer Angewandte Informatik; Schoenecker, H.; Krakau, T. [ci-Tec GmbH, Karlsruhe (Germany)

    2007-07-01

    The application of modern procedures for control and regulation at industrial procedures requires the knowledge of important process variables which are not measurable on-line. Optical measurements by means of video cameras and infrared cameras enable a non-destructive observation of the combustion process in locally different developments. Thus, process variables can be determined by means of special software of image processing in real time. For grate firings and rotating kilns, INSPECT applications are developed. The characteristics computed thereby directly can be used by means of a Fuzzy control module or by external systems for the optimization of the firing regulation. The enormous potential of the optimization with the INSPECT system impressively is confirmed by the past installations and by the process improvements obtained thereby. The INSPECT system was developed in co-operation with Ci-Tec GmbH (Ratingen, Federal Republic of Germany) and marketed, maintained and further developed by Ci-Tec GmbH.

  18. An automated eddy current in-service inspection system for nuclear steam generator tubing

    International Nuclear Information System (INIS)

    Wells, N.S.

    1981-06-01

    A prototype steam generator in-service inspection system incorporating remotely-controlled instrumentation linked by a digital transmission line to an instrument and control trailer outside the reactor containment has been designed and manufactured and is presently undergoing field tests. The (Monel 400) steam generator tubes are scanned two at a time using absolute eddy current probes controlled by two remotely-operated probe drives at a scanning speed of 0.5 m/s. The probes are positioned on the tubesheet by a light-weight (1.5 kg) microprocessor-operated tubesheet walker mechanism. Digitized control and data signals are transmitted up to 300 m to the control trailer. There the control and analysis computers extract the relevant signal information and present it in condensed form as labelled graphics on CRT consoles for on-line visual assessment. Hard copy output is also provided for each tube scanned (one per minute). Condensed data is archived on magnetic tapes for additional off-line analysis and comparisons with other inspections

  19. Pulley system including emergency locking means for nuclear reactor vessel inspection apparatus

    International Nuclear Information System (INIS)

    Reyes, R.D.

    1979-01-01

    A pulley system for driving the manipulating arm of a nuclear reactor vessel inspection device is disclosed. Two drive pulleys and pulley take-up spools are disposed in driving engagement with a motor. The pulley cable is looped about a first set of idler pulleys fixed to the manipulator arm which is to be driven along the main or central column of the inspection device. Two additional idler pulleys, a second set, are used to define another portion of the pulley cable loop, which portion serves to equalize unbalanced forces in the cable. When the drive motor is actuated, only that portion of the pulley cable between the drive set and the first set of idler pulleys moves. Depending on the direction of movement, the manipulator arm is raised or lowered with equal force on each side thereof minimizing wear and potential hazards. In addition, to guard against the possible dangers resulting from a snapped pulley cable, a restraining clip is secured to the cable between the second set of idler pulleys and is appropriately sized to jam between one of the idler pulleys and its support bracket. 3 claims

  20. Development of a lens-coupled CMOS detector for an X-ray inspection system

    International Nuclear Information System (INIS)

    Kim, Ho Kyung; Ahn, Jung Keun; Cho, Gyuseong

    2005-01-01

    A digital X-ray imaging detector based on a complementary metal-oxide-semiconductor (CMOS) image sensor has been developed for X-ray non-destructive inspection applications. This is a cost-effective solution because of the availability of cheap commercial standard CMOS image sensors. The detector configuration adopts an indirect X-ray detection method by using scintillation material and lens assembly. As a feasibility test of the developed lens-coupled CMOS detector as an X-ray inspection system, we have acquired X-ray projection images under a variety of imaging conditions. The results show that the projected image is reasonably acceptable in typical non-destructive testing (NDT). However, the developed detector may not be appropriate for laminography due to a low light-collection efficiency of lens assembly. In this paper, construction of the lens-coupled CMOS detector and its specifications are described, and the experimental results are presented. Using the analysis of quantum accounting diagram, inefficiency of the lens-coupling method is discussed

  1. The EBR-II steam generating system - operation, maintenance, and inspection

    International Nuclear Information System (INIS)

    Buschman, H.W.; Penney, W.H.; Longua, K.J.

    2002-01-01

    The Experimental Breeder Reactor II (EBR-II) has operated for 20 years at the Idaho National Engineering Laboratory near Idaho Falls. EBR-II is a Liquid Metal Fast Breeder Reactor (LMFBR) with integrated power producing capability. EBR-II has operated at a capacity factor over 70% in the past few years. Superheated steam is produced by eight natural circulation evaporators, two superheaters, and a conventional steam drum. Steam throttle conditions are 438 C and 8.62 MPa. The designs of the evaporators and superheaters are essentially identical; both are counterflow units with low pressure nonradioactive sodium on the shell side. During the 20 years of operation, components of the steam generator have been subjected to a variety of inspections including visual, dimensional, and ultrasonic. One superheater was removed from service because of anomalous performance and was replaced with an evaporator which was removed, examined, and converted into a superheater. Overall operating experience of the system has been excellent and essentially trouble free. Inspections have not revealed any conditions that are performance or life limiting. (author)

  2. Applicability of Clearance Automatic Laser Inspection System to Clearance Measurement of Concrete Segments

    International Nuclear Information System (INIS)

    Sasaki, M.; Ogino, H.; Hattori, T.

    2009-01-01

    In the decommissioning of a nuclear power plant, large amounts of metal scrap and concrete segments require disposal when dismantling the nuclear reactor and surrounding facilities. When their activity level is negligible or sufficiently small, they can be regarded as general industrial waste. To distinguish between radioactive and nonradioactive materials, the clearance level for each radionuclide has been determined in units of activity concentration. These clearance levels are indicated in the International Atomic Energy Agency (IAEA) Safety Standards Series No. RS-G-1.7. The Japanese regulatory authority decided in 2005 to adopt the values given in RS-G-1.7 as clearance levels in legislation. Recently, a Clearance Automatic Laser Inspection System (CLALIS) has been developed utilizing gamma-ray measurement, automatic laser shape measurement and Monte Carlo calculation. CLALIS comprises four laser scanners and eight large plastic scintillation detectors surrounded by a 5-cm-thick lead shield. Using three-dimensional (3D) laser scanning, a measurement target, which is placed on the measuring tray, is represented as a dot image. The dot image is converted into voxels after noise removal, and is written in MCNP (A General Monte Carlo N-Particle Transport Code System) input files. When the gamma-ray measurement is carried out, the MCNP calculations are also carried out to obtain the calibration factor and background (BG) correction factors. For the clearance measurement of concrete segments, the effect of gamma-rays from natural radionuclides in the measurement target, such as K-40 and the radioactive decay products of Th-232 and U-238, should be taken into account to ensure adequate waste management. Since NE102A plastic scintillation detectors are used for gamma-ray measurement in CLALIS, it is impossible to distinguish between the count rates of natural radionuclides and contaminants on the basis of gamma-ray energy information. To overcome this problem, the

  3. High Pressure Coolant Injection system risk-based inspection guide for Hatch Nuclear Power Station

    International Nuclear Information System (INIS)

    DiBiasio, A.M.

    1993-05-01

    A review of the operating experience for the High Pressure Coolant Injection (HPCI) system at the Hatch Nuclear Power Station, Units 1 and 2, is described in this report. The information for this review was obtained from Hatch Licensee Event Reports (LERs) that were generated between 1980 and 1992. These LERs have been categorized into 23 failure modes that have been prioritized based on probabilistic risk assessment considerations. In addition, the results of the Hatch operating experience review have been compared with the results of a similar, industry wide operating, experience review. This comparison provides an indication of areas in the Hatch HPCI system that should be given increased attention in the prioritization of inspection resources

  4. Characteristics of electron gun used in the accelerator for customs inspection systems

    International Nuclear Information System (INIS)

    Huang Weiling; Li Quanfeng; Zhang Yunkai

    2001-01-01

    The author introduces the characteristics of the electron gun used in the 9 MeV traveling wave electron linear accelerator for fixed customs container inspection system. With the scan date cathode, the electron gun meets the accelerator characteristics with the whole system not needing high-temperature roasting to degas. The electron gun can work normally at a vacuum of about 10 -5 Pa and can be reinstalled after exposure to air. In the accelerator, the electron gun emits a beam which strikes the target to produce an X-ray beam with a dosage rate of over 30 Gy/(min·m) and a beam focus spot of less than φ 2 mm. The EGUN code is used to simulate the structure and properties of the electron gun. The reference size debugging parameters for replacing the electron gun are given for assembly requirements

  5. Simulation of Specular Surface Imaging Based on Computer Graphics: Application on a Vision Inspection System

    Directory of Open Access Journals (Sweden)

    Seulin Ralph

    2002-01-01

    Full Text Available This work aims at detecting surface defects on reflecting industrial parts. A machine vision system, performing the detection of geometric aspect surface defects, is completely described. The revealing of defects is realized by a particular lighting device. It has been carefully designed to ensure the imaging of defects. The lighting system simplifies a lot the image processing for defect segmentation and so a real-time inspection of reflective products is possible. To bring help in the conception of imaging conditions, a complete simulation is proposed. The simulation, based on computer graphics, enables the rendering of realistic images. Simulation provides here a very efficient way to perform tests compared to the numerous attempts of manual experiments.

  6. Condition-based inspection/replacement policies for non-monotone deteriorating systems with environmental covariates

    Energy Technology Data Exchange (ETDEWEB)

    Zhao Xuejing [Universite de Technologie de Troyes, Institut Charles Delaunay and STMR UMR CNRS 6279, 12 rue Marie Curie, 10010 Troyes (France); School of mathematics and statistics, Lanzhou University, Lanzhou 730000 (China); Fouladirad, Mitra, E-mail: mitra.fouladirad@utt.f [Universite de Technologie de Troyes, Institut Charles Delaunay and STMR UMR CNRS 6279, 12 rue Marie Curie, 10010 Troyes (France); Berenguer, Christophe [Universite de Technologie de Troyes, Institut Charles Delaunay and STMR UMR CNRS 6279, 12 rue Marie Curie, 10010 Troyes (France); Bordes, Laurent [Universite de Pau et des Pays de l' Adour, LMA UMR CNRS 5142, 64013 PAU Cedex (France)

    2010-08-15

    The aim of this paper is to discuss the problem of modelling and optimising condition-based maintenance policies for a deteriorating system in presence of covariates. The deterioration is modelled by a non-monotone stochastic process. The covariates process is assumed to be a time-homogenous Markov chain with finite state space. A model similar to the proportional hazards model is used to show the influence of covariates on the deterioration. In the framework of the system under consideration, an appropriate inspection/replacement policy which minimises the expected average maintenance cost is derived. The average cost under different conditions of covariates and different maintenance policies is analysed through simulation experiments to compare the policies performances.

  7. Condition-based inspection/replacement policies for non-monotone deteriorating systems with environmental covariates

    International Nuclear Information System (INIS)

    Zhao Xuejing; Fouladirad, Mitra; Berenguer, Christophe; Bordes, Laurent

    2010-01-01

    The aim of this paper is to discuss the problem of modelling and optimising condition-based maintenance policies for a deteriorating system in presence of covariates. The deterioration is modelled by a non-monotone stochastic process. The covariates process is assumed to be a time-homogenous Markov chain with finite state space. A model similar to the proportional hazards model is used to show the influence of covariates on the deterioration. In the framework of the system under consideration, an appropriate inspection/replacement policy which minimises the expected average maintenance cost is derived. The average cost under different conditions of covariates and different maintenance policies is analysed through simulation experiments to compare the policies performances.

  8. 5th International Conference on Complex Systems

    CERN Document Server

    Braha, Dan; Bar-Yam, Yaneer

    2011-01-01

    The International Conference on Complex Systems (ICCS) creates a unique atmosphere for scientists of all fields, engineers, physicians, executives, and a host of other professionals to explore common themes and applications of complex system science. With this new volume, Unifying Themes in Complex Systems continues to build common ground between the wide-ranging domains of complex system science.

  9. 7th International Conference on Complex Systems

    CERN Document Server

    Braha, Dan; Bar-Yam, Yaneer

    2012-01-01

    The International Conference on Complex Systems (ICCS) creates a unique atmosphere for scientists of all fields, engineers, physicians, executives, and a host of other professionals to explore common themes and applications of complex system science. With this new volume, Unifying Themes in Complex Systems continues to build common ground between the wide-ranging domains of complex system science.

  10. 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

  11. Design and application of radiation apparatus for sup 6 sup 0 Co cargo train on-line inspection system

    CERN Document Server

    Wu Zhi Fang; Zhang Yuai

    2002-01-01

    Based on the special requirement for radiation apparatus of sup 6 sup 0 Co cargo train on-line inspection system, a radiation apparatus including two-level shutter, working container, storing container and electromagnetism are designed. The makeup, working mode and functional realization of the radiation apparatus are introduced. The system is used in Manzhouli customs cargo train on-line inspection system. The practice shows that the radiation apparatus is reliable to work steadily and the operating speed of the main shutter can reach 0.1 s open and 0.15 s close

  12. Development and operational experiences of an automated remote inspection system for interior of primary containment vessel of a BWR

    International Nuclear Information System (INIS)

    Ozaki, N.; Chikara, S.; Fumio, T.; Katsuhiro, M.; Katsutoshi, S.; Ken-Ichiro, S.; Masaaki, F.; Masayoshi, S.

    1983-01-01

    A prototype was developed for an automated remote inspection system featuring continuous monitoring of the working status of major components inside the primary containment vessel of a boiling water reactor. This inspection system consists of four units, or vehicles, which are towed by a trolley chain along a monorail; a complex coaxial cable for data transmission and for power supply; and an operator's console. A TV camera, microphone, thermometer, hygrometer, and ionization chamber are mounted on the various units. After several months' testing under high-ambient temperature, the system was installed in the Tokai-2 power station of Japan Atomic Power Company for in situ tests

  13. Nondestructive Inspection System for Special Nuclear Material Using Inertial Electrostatic Confinement Fusion Neutrons and Laser Compton Scattering Gamma-Rays

    Science.gov (United States)

    Ohgaki, H.; Daito, I.; Zen, H.; Kii, T.; Masuda, K.; Misawa, T.; Hajima, R.; Hayakawa, T.; Shizuma, T.; Kando, M.; Fujimoto, S.

    2017-07-01

    A Neutron/Gamma-ray combined inspection system for hidden special nuclear materials (SNMs) in cargo containers has been developed under a program of Japan Science and Technology Agency in Japan. This inspection system consists of an active neutron-detection system for fast screening and a laser Compton backscattering gamma-ray source in coupling with nuclear resonance fluorescence (NRF) method for precise inspection. The inertial electrostatic confinement fusion device has been adopted as a neutron source and two neutron-detection methods, delayed neutron noise analysis method and high-energy neutron-detection method, have been developed to realize the fast screening system. The prototype system has been constructed and tested in the Reactor Research Institute, Kyoto University. For the generation of the laser Compton backscattering gamma-ray beam, a race track microtron accelerator has been used to reduce the size of the system. For the NRF measurement, an array of LaBr3(Ce) scintillation detectors has been adopted to realize a low-cost detection system. The prototype of the gamma-ray system has been demonstrated in the Kansai Photon Science Institute, National Institutes for Quantum and Radiological Science and Technology. By using numerical simulations based on the data taken from these prototype systems and the inspection-flow, the system designed by this program can detect 1 kg of highly enriched 235U (HEU) hidden in an empty 20-ft container within several minutes.

  14. Development of the Automated Ultrasonic Testing System for Inspection of the flaw in the Socket Weldment

    International Nuclear Information System (INIS)

    Lee, Jeong Ki; Park, Moon Ho; Park, Ki Sung; Lee, Jae Ho; Lim, Sung Jin

    2004-01-01

    Socket weldment used to change the flow direction of fluid nay have flaws such as lack of fusion and cracks. Liquid penetrant testing or Radiography testing have been applied as NDT methods for flaw detection of the socket weldment. But it is difficult to detect the flaw inside of the socket weldment with these methods. In order to inspect the flaws inside the socket weldment, a ultrasonic testing method is established and a ultrasonic transducer and automated ultrasonic testing system are developed for the inspection. The automated ultrasonic testing system is based on the portable personal computer and operated by the program based Windows 98 or 2000. The system has a pulser/receiver, 100MHz high speed A/D board, and basic functions of ultrasonic flaw detector using the program. For the automated testing, motion controller board of ISA interface type is developed to control the 4-axis scanner and a real time iC-scan image of the automated testing is displayed on the monitor. A flaws with the size of less than 1mm in depth are evaluated smaller than its actual site in the testing, but the flaws larger than 1mm appear larger than its actual size on the contrary. This tendency is shown to be increasing as the flaw size increases. h reliable and objective testing results are obtained with the developed system, so that it is expected that it can contribute to safety management and detection of repair position of pipe lines of nuclear power plants and chemical plants

  15. Sampling inspection for the evaluation of time-dependent reliability of deteriorating systems under imperfect defect detection

    International Nuclear Information System (INIS)

    Kuniewski, Sebastian P.; Weide, Johannes A.M. van der; Noortwijk, Jan M. van

    2009-01-01

    The paper presents a sampling-inspection strategy for the evaluation of time-dependent reliability of deteriorating systems, where the deterioration is assumed to initiate at random times and at random locations. After initiation, defects are weakening the system's resistance. The system becomes unacceptable when at least one defect reaches a critical depth. The defects are assumed to initiate at random times modeled as event times of a non-homogeneous Poisson process (NHPP) and to develop according to a non-decreasing time-dependent gamma process. The intensity rate of the NHPP is assumed to be a combination of a known time-dependent shape function and an unknown proportionality constant. When sampling inspection (i.e. inspection of a selected subregion of the system) results in a number of defect initiations, Bayes' theorem can be used to update prior beliefs about the proportionality constant of the NHPP intensity rate to the posterior distribution. On the basis of a time- and space-dependent Poisson process for the defect initiation, an adaptive Bayesian model for sampling inspection is developed to determine the predictive probability distribution of the time to failure. A potential application is, for instance, the inspection of a large vessel or pipeline suffering pitting/localized corrosion in the oil industry. The possibility of imperfect defect detection is also incorporated in the model.

  16. Gypsum plasterboard walls: inspection, pathological characterization and statistical survey using an expert system

    Directory of Open Access Journals (Sweden)

    Gaião, C.

    2012-06-01

    Full Text Available This paper presents an expert system to support the inspection and diagnosis of partition walls or wall coverings mounted using the Drywall (DW construction method. This system includes a classification of anomalies in DW and their probable causes. This inspection system was used in a field work that included the observation of 121 DWs. This paper includes a statistical analysis of the anomalies observed during these inspections and their probable causes. The correlation between anomalies and causes in the sample is also thoroughly analyzed. Anomalies are also evaluated for area affected, size, repair urgency and aesthetic value of the affected area. The conclusions of the statistical analysis allowed the creation of an inventory of preventive measures to be implemented in the design, execution and use phases in order to lessen the magnitude or eradicate the occurrence of anomalies in DW. These measures could directly help improve the quality of construction.

    Este trabajo presenta un sistema experto de apoyo a la inspección y diagnóstico de tabiques o revestimientos de yeso laminado. Dicho sistema, que permite la clasificación de las anomalías del yeso laminado y sus causas probables, se empleó en un trabajo de campo en el que se estudiaron 121 elementos construidos con este material. El trabajo incluye el análisis estadístico de las anomalías detectadas durante las inspecciones y sus motivos probables. También se analizó en detalle la correlación entre las anomalías y sus causas, evaluándose aquellas en función de la superficie afectada, la urgencia de las reparaciones y el valor estético de la zona implicada. Las conclusiones del análisis estadístico permitieron la elaboración de un inventario de medidas preventivas que deberían implantarse en las fases de proyecto, ejecución y utilización de estos elementos a fin de erradicar la aparición de anomalías en el yeso laminado o reducir su frecuencia. Dichas

  17. NRC Information Notice No. 91-29, Supplement 1: Deficiencies identified during electrical distribution system functional inspections

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1993-01-01

    During multidiscipline inspections such as safety system functional inspections (SSFIs) or safety system outage modification inspections (SSOMIs), the NRC identified a number of deficiencies related to the electrical distribution system (EDS). As a result of these deficiencies, the NRC developed the EDSFI to specifically evaluate the EDS. Since 1989, the NRC has performed over 50 EDSFIs, and found design weaknesses in the following generic areas: (1) undervoltage relay setpoints for degraded grid conditions; (2) interrupting capacity of fault protection devices; (3) improper coordination of fault protection devices; (4) analysis of emergency diesel generator (EDG) capacity to power safety-related loads during postulated accidents; and (5) EDG mechanical interfaces. Each of these issues are discussed

  18. 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

  19. 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

  20. Ultrasound and Eddy-Current inspection of longitudinal shroud welds in the Santa Maria de Garona Nuclear Power Plant

    International Nuclear Information System (INIS)

    Elorza, J.; Fernandez, F.

    1998-01-01

    This is the first time that this kind of inspection has been performed in the world with the Ultrasound (UT) and Eddy-Current (EC) techniques. The inspection, performed during the 19th refueling outage in March 1997, using the MIDAS acquisition and analysis system, which allows joint UT and EC inspection. MIDAS is the new inspection system developed by Tecnatom for vessel internals that integrates acquisition and evaluation of the data obtained from the use of Ultrasound and Eddy-Current inspection techniques. The inspection was completed in less than the scheduled time, and covered the programmed volumes without any noteworthy incidents. (Author)

  1. Automated ultrasonic pipe weld inspection. Part 1

    International Nuclear Information System (INIS)

    Karl Deutsch, W.A.; Schulte, P.; Joswig, M.; Kattwinkel, R.

    2006-01-01

    This article contains a brief overview on automated ultrasonic welded inspection for various pipe types. Some inspection steps might by carried out with portable test equipment (e.g. pipe and test), but the weld inspection in all internationally relevant specification must be automated. The pipe geometry, the production process, and the pipe usage determine the number of required probes. Recent updates for some test specifications enforce a large number of ultrasonic probes, e.g. the Shell standard. Since seamless pipes are sometimes replaced by ERW pipes and LSAW pipes (in both cases to save production cost), the inspection methods change gradually between the various pipe types. Each testing system is unique and shows its specialties which have to be discussed by supplier, testing system user and final customer of the pipe. (author)

  2. 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...

  3. A television/still camera with common optical system for reactor inspection

    International Nuclear Information System (INIS)

    Hughes, G.; McBane, P.

    1976-01-01

    One of the problems of reactor inspection is to obtain permanent high quality records. Video recordings provide a record of poor quality but known content. Still cameras can be used but the frame content is not predictable. Efforts have been made to combine T.V. viewing to align a still camera but a simple combination does not provide the same frame size. The necessity to preset the still camera controls severely restricts the flexibility of operation. A camera has, therefore, been designed which allows a search operation using the T.V. system. When an anomaly is found the still camera controls can be remotely set, an exact record obtained and the search operation continued without removal from the reactor. An application of this camera in the environment of the blanket gas region above the sodium region in PFR at 150 0 C is described

  4. Automation of eddy current system for in-service inspection of turbine and generator rotor bores

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The current project (EPRI-RP-1975-5) is a continuation of activities that began several years ago. Those results (EPRI-RP-1957-1) indicated that eddy current testing shows promise for in-service inspection. The current project investigates the degree to which eddy current testing can be used to replace bore magnetic particle testing. For this purpose, correlation studies between eddy current and magnetic particle tests are being undertaken on laboratory rotor sections and field test pieces of rotors. The eddy current data are to be gathered automatically by a combination of the Nortec-25L Eddyscope (to provide the analog eddy current signals) and the General Electric DATAQ/sup TM/ (a registered trademark of the General Electric Co.) System (to perform the automatic data acquisition). This paper describes some test results on a flaked laboratory rotor section

  5. National system of notification, authorization and inspection for the control of radiation sources in Ghana

    International Nuclear Information System (INIS)

    Schandorf, C.; Darko, E.O.; Yeboah, J.; Asiamah, S.D.

    2001-01-01

    The Radiation Protection Board (RPB) was established in 1993 in Ghana as the regulatory authority for radiation protection and safety of radiation sources; its functions are prescribed in the 1993 national radiation protection regulation. The report describes how the country's radiation protection and safety infrastructure have been established, including the RPB's organizational structure, with reference in particular to the main activities carried out by both the Regulatory Control Department and the Radiation and Waste Safety Department. It also briefly mentions the existing RPB human resources; the national system of notification, authorization and inspection of radiation sources; the inventory of radiation sources; and the management of disused radiation sources. Finally, the report identifies the two main problem areas regarding the regulatory control of radiation sources in the country. (author)

  6. Decentralized real time control system of inspection robot programmed in APL

    International Nuclear Information System (INIS)

    Dupeyrat, Benoit; Liabot, M.J.; Vertut, Jean

    1979-01-01

    The running of the SUPER PHENIX vessel inspection robot meets with special practical necessities: the distance between the robot and the computer responsible for its management is important since the piloting station is outside the safety enclosure. For this reason the control and alarm functions have been separated from those of strategy and readjustment. The system described here is thus made up of: a mini-computer to manage the piloting station and a microprocessor as close as possible to the machine for control and safety duties. This arrangement has the advantage of limiting the input/output volume of the mini-computer which can thus be programmed in APL, a language particularly efficient and well suited to the problem [fr

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

    International Nuclear Information System (INIS)

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

    1983-01-01

    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

  8. 23rd International Conference on Systems Engineering

    CERN Document Server

    Zydek, Dawid; Chmaj, Grzegorz

    2015-01-01

    This collection of proceedings from the International Conference on Systems Engineering, Las Vegas, 2014 is orientated toward systems engineering, including topics like aerospace, power systems, industrial automation and robotics, systems theory, control theory, artificial intelligence, signal processing, decision support, pattern recognition and machine learning, information and communication technologies, image processing, and computer vision as well as its applications. The volume’s main focus is on models, algorithms, and software tools that facilitate efficient and convenient utilization of modern achievements in systems engineering.

  9. Flight route Designing and mission planning Of power line inspecting system Based On multi-sensor UAV

    International Nuclear Information System (INIS)

    Xiaowei, Xie; Zhengjun, Liu; Zhiquan, Zuo

    2014-01-01

    In order to obtain various information of power facilities such as spatial location, geometry, images data and video information in the infrared and ultraviolet band and so on, Unmanned Aerial Vehicle (UAV) power line inspecting system needs to integrate a variety of sensors for data collection. Low altitude and side-looking imaging are required for UAV flight to ensure sensors to acquire high-quality data and device security. In this paper, UAV power line inspecting system is deferent from existing ones that used in Surveying and Mapping. According to characteristics of UAV for example equipped multiple sensor, side-looking imaging, working at low altitude, complex terrain conditions and corridor type flight, this paper puts forward a UAV power line inspecting scheme which comprehensively considered of the UAV performance, sensor parameters and task requirements. The scheme is finally tested in a region of Guangdong province, and the preliminary results show that the scheme is feasible

  10. 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)

  11. Recent experiences with ultrasonic inservice inspection systems with phased array probes on spherical bottoms of boiling water reactors

    International Nuclear Information System (INIS)

    Wustenberg, H.; Brekow, G.; Erhard, A.; Hein, E.

    1988-01-01

    The special geometry of the spherical bottom of boiling water reactors with control rods and measuring nozzles requires a very special surveillance technique during the in-service inspection. Reside visual inspection an ultrasonic inspection has been established due to the requirements of German authorities. A first application of a new phased array system took place August 1987. The 100% inspection of a spherical bottom had been enabled by the application of phased array probes with electronically controlled skewing angles. The data acquisition had been based on the storage of whole A-scans, which had been pixellized into 256 points. This A-scan storage procedure makes possible the application of a simple and fast algorithm to present the data as TD-(time displacement)-scans. Defect reconstruction by echotomographique approaches are under development. This paper presents the ultrasonic technique applied including the phased array probes, the electronic system, as well as the software package used for the control of the inspection parameters depending on the probe position

  12. Development of bore tools for pipe inspection

    Energy Technology Data Exchange (ETDEWEB)

    Oka, Kiyoshi; Nakahira, Masataka; Taguchi, Kou; Ito, Akira [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-04-01

    In the International Thermonuclear Reactor (ITER), replacement and maintenance on in-vessel components requires that all cooling pipes connected be cut and removed, that a new component be installed, and that all cooling pipes be rewelded. After welding is completed, welded area must be inspected for soundness. These tasks require a new work concept for securing shielded area and access from narrow ports. Tools had to be developed for nondestructive inspection and leak testing to evaluate pipe welding soundness by accessing areas from inside pipes using autonomous locomotion welding and cutting tools. A system was proposed for nondestructive inspection of branch pipes and the main pipe after passing through pipe curves, the same as for welding and cutting tool development. Nondestructive inspection and leak testing sensors were developed and the basic parameters were obtained. In addition, the inspection systems which can move inside pipes and conduct the nondestructive inspection and the leak testing were developed. In this paper, an introduction will be given to the current situation concerning the development of nondestructive inspection and leak testing machines for the branch pipes. (author)

  13. A feasibility study of stateful automaton packet inspection for streaming application detection systems

    Science.gov (United States)

    Tseng, Kuo-Kun; Lo, Jiao; Liu, Yiming; Chang, Shih-Hao; Merabti, Madjid; Ng, Felix, C. K.; Wu, C. H.

    2017-10-01

    The rapid development of the internet has brought huge benefits and social impacts; however, internet security has also become a great problem for users, since traditional approaches to packet classification cannot achieve satisfactory detection performance due to their low accuracy and efficiency. In this paper, a new stateful packet inspection method is introduced, which can be embedded in the network gateway and used by a streaming application detection system. This new detection method leverages the inexact automaton approach, using part of the header field and part of the application layer data of a packet. Based on this approach, an advanced detection system is proposed for streaming applications. The workflow of the system involves two stages: the training stage and the detection stage. In the training stage, the system initially captures characteristic patterns from a set of application packet flows. After this training is completed, the detection stage allows the user to detect the target application by capturing new application flows. This new detection approach is also evaluated using experimental analysis; the results of this analysis show that this new approach not only simplifies the management of the state detection system, but also improves the accuracy of data flow detection, making it feasible for real-world network applications.

  14. Mobile CT system for in-situ inspection of the LHC at CERN

    International Nuclear Information System (INIS)

    Sauerwein, Christoph; Haemmerle, Volker; Tiseanu, Ion; Williams, Lloyd R.; Caspers, Fritz

    2010-01-01

    The world's biggest particle accelerator, the Large Hadron Collider (LHC) was recently commissioned at CERN. It was found that a condition monitoring system for its connecting elements would be useful. A monitoring system of this kind must be able to function without opening connecting elements, without breaking the vacuum, and without heating up the inspection sector as this would be too costly and time-consuming. Further, the system should be mobile in order to be applicable in all positions of the 27 km long accelerator. A radiographic system will be used, with the intention to get an identifiable image of all structures in the connecting elements of the accelerator. The minimum requirement is an image that enables an assessment of the structural integrity and correct position of all important components. 3D CT is the ideal solution, but owing to the limited space it is impossible to move an X-ray tube and detector completely around the connecting elements. A mobile 3D CT unit was therefore developed which enables maximum scanning variety within the given limits and provides 3D images based on a strongly limited range of scanning angles. The system is described in the paper, along with the results achieved so far and with an outlook onto further applications. (orig.)

  15. Development of a Versatile Ultrasonic Internal Pipe/Vessel Component Monitor for In-Service Inspection of Nuclear Reactor Components

    Energy Technology Data Exchange (ETDEWEB)

    Searfass, Clifford T. [Structural Integrity Associates, Inc., State College, PA (United States); Malinowski, Owen M. [Structural Integrity Associates, Inc., State College, PA (United States); Van Velsor, Jason K. [Structural Integrity Associates, Inc., State College, PA (United States)

    2015-03-22

    The stated goal of this work was to develop a versatile system which could accurately measure vessel and valve internal vibrations and cavitation formation under in-service conditions in nuclear power plants, ultrasonically. The developed technology will benefit the nuclear power generation industry by allowing plant operators to monitor valve and vessel internals during operation. This will help reduce planned outages and plant component failures. During the course of this work, Structural Integrity Associates, Inc. gathered information from industry experts that target vibration amplitudes to be detected should be in the range of 0.001-in to 0.005-in (0.025-mm to 0.127-mm) and target vibration frequency ranges which should be detected were found to be between 0-Hz and 300-Hz. During the performed work, an ultrasonic measuring system was developed which utilized ultrasonic pulse-echo time-of-flight measurements to measure vibration frequency and amplitude. The developed system has been shown to be able to measure vibration amplitudes as low as 0.0008-in (0.020-mm) with vibration frequencies in the range of 17-Hz to 1000-Hz. Therefore, the developed system was able to meet the industry needs for vibration measurement. The developed ultrasonic system was also to be able to measure cavitation formation by monitoring the received ultrasonic time- and frequency-domain signals. This work also demonstrated the survivability of commercially available probes at temperatures up to 300-F for several weeks.

  16. Relationship between the international marketing research and the international marketing information system

    OpenAIRE

    Grubor Aleksandar

    2004-01-01

    Real and complete understanding relationship between the international marketing research and the international marketing information system requires recognizing essentials of the both concept. The international marketing research constitutes a process with coherent phases, whereas the international marketing information system is a part of integrated company's information system. Approach to learning relationship between the international marketing research and the international marketing in...

  17. Pipelines inspection robots; Robos para inspecao de linhas de servico

    Energy Technology Data Exchange (ETDEWEB)

    Archila Diaz, John Faber; Dutra, Max Suell [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Lab. de Robotica

    2008-07-01

    One of the problems existing in the area of maintenance of systems for the transport of mass and / or energy is to examine the integrity of the lines of service in the basic infrastructure of cities and industries. For the development of maintenance, whether predictive, preventive or corrective is necessary to conduct the inspection of these lines. To carry out this task is necessary count on help of appropriate technological tools. The main tools for inspection of service lines come from the area of external inspection of pipelines and are also in development, the problem happens when we need to achieve internal or external failures in places of difficult access, and move the inspection equipment to places where it's going to fail. In these cases it is necessary to the use of mechatronic systems, more specifically robotic systems, which may be developed for inspection. This paper aims to present the main robotic systems used for inspection, especially for internal inspection of pipelines. These systems have been developed by the research groups in Brazil, Japan, and Belgium among others, giving up a classification of robots for inspection of pipelines and the main features necessary for its project. (author)

  18. Pipelines inspection robots; Robos para inspecao de linhas de servico

    Energy Technology Data Exchange (ETDEWEB)

    Archila Diaz, John Faber; Dutra, Max Suell [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Lab. de Robotica

    2008-07-01

    One of the problems existing in the area of maintenance of systems for the transport of mass and / or energy is to examine the integrity of the lines of service in the basic infrastructure of cities and industries. For the development of maintenance, whether predictive, preventive or corrective is necessary to conduct the inspection of these lines. To carry out this task is necessary count on help of appropriate technological tools. The main tools for inspection of service lines come from the area of external inspection of pipelines and are also in development, the problem happens when we need to achieve internal or external failures in places of difficult access, and move the inspection equipment to places where it's going to fail. In these cases it is necessary to the use of mechatronic systems, more specifically robotic systems, which may be developed for inspection. This paper aims to present the main robotic systems used for inspection, especially for internal inspection of pipelines. These systems have been developed by the research groups in Brazil, Japan, and Belgium among others, giving up a classification of robots for inspection of pipelines and the main features necessary for its project. (author)

  19. Real-time line-width measurements: a new feature for reticle inspection systems

    Science.gov (United States)

    Eran, Yair; Greenberg, Gad; Joseph, Amnon; Lustig, Cornel; Mizrahi, Eyal

    1997-07-01

    The significance of line width control in mask production has become greater with the lessening of defect size. There are two conventional methods used for controlling line widths dimensions which employed in the manufacturing of masks for sub micron devices. These two methods are the critical dimensions (CD) measurement and the detection of edge defects. Achieving reliable and accurate control of line width errors is one of the most challenging tasks in mask production. Neither of the two methods cited above (namely CD measurement and the detection of edge defects) guarantees the detection of line width errors with good sensitivity over the whole mask area. This stems from the fact that CD measurement provides only statistical data on the mask features whereas applying edge defect detection method checks defects on each edge by itself, and does not supply information on the combined result of error detection on two adjacent edges. For example, a combination of a small edge defect together with a CD non- uniformity which are both within the allowed tolerance, may yield a significant line width error, which will not be detected using the conventional methods (see figure 1). A new approach for the detection of line width errors which overcomes this difficulty is presented. Based on this approach, a new sensitive line width error detector was developed and added to Orbot's RT-8000 die-to-database reticle inspection system. This innovative detector operates continuously during the mask inspection process and scans (inspects) the entire area of the reticle for line width errors. The detection is based on a comparison of measured line width that are taken on both the design database and the scanned image of the reticle. In section 2, the motivation for developing this new detector is presented. The section covers an analysis of various defect types, which are difficult to detect using conventional edge detection methods or, alternatively, CD measurements. In section 3

  20. 14 CFR Appendix E to Part 43 - Altimeter System Test and Inspection

    Science.gov (United States)

    2010-01-01

    ... associated computing systems, or which incorporate air data correction internally, may be tested in a manner...) Automatic Pressure Altitude Reporting Equipment and ATC Transponder System Integration Test. The test must...). Measure the automatic pressure altitude at the output of the installed ATC transponder when interrogated...