WorldWideScience

Sample records for current inspection system

  1. 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.

  2. 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.

  3. 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

  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. An Eddy Current Testing Platform System for Pipe Defect Inspection Based on an Optimized Eddy Current Technique Probe Design

    Science.gov (United States)

    Rifai, Damhuji; Abdalla, Ahmed N.; Razali, Ramdan; Ali, Kharudin; Faraj, Moneer A.

    2017-01-01

    The use of the eddy current technique (ECT) for the non-destructive testing of conducting materials has become increasingly important in the past few years. The use of the non-destructive ECT plays a key role in the ensuring the safety and integrity of the large industrial structures such as oil and gas pipelines. This paper introduce a novel ECT probe design integrated with the distributed ECT inspection system (DSECT) use for crack inspection on inner ferromagnetic pipes. The system consists of an array of giant magneto-resistive (GMR) sensors, a pneumatic system, a rotating magnetic field excitation source and a host PC acting as the data analysis center. Probe design parameters, namely probe diameter, an excitation coil and the number of GMR sensors in the array sensor is optimized using numerical optimization based on the desirability approach. The main benefits of DSECT can be seen in terms of its modularity and flexibility for the use of different types of magnetic transducers/sensors, and signals of a different nature with either digital or analog outputs, making it suited for the ECT probe design using an array of GMR magnetic sensors. A real-time application of the DSECT distributed system for ECT inspection can be exploited for the inspection of 70 mm carbon steel pipe. In order to predict the axial and circumference defect detection, a mathematical model is developed based on the technique known as response surface methodology (RSM). The inspection results of a carbon steel pipe sample with artificial defects indicate that the system design is highly efficient. PMID:28335399

  6. 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

  7. 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)

  8. 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

  9. Pulsed eddy current inspection system for nondestructive examination of irradiated fuel rods

    International Nuclear Information System (INIS)

    Yancey, M.E.

    1979-01-01

    An inspection system has been developed for nondestructive examination of irradiated fuel rods utilizing pulsed eddy current techniques. The system employs an encircling type pulsed eddy current transducer capable of sensing small defects located on both the inner and outer diameter fuel rod surfaces during a single scan. Pulsed eddy current point probes are used to provide fuel rod wall thikness data and an indication of radial defect location. Two linear variable differential transformers are used to provide information on fuel rod diameter variation. A microprocessor based control system is used to automatically scan fuel rods up to 4.06 meters in length at predetermined radial locations. Defects as small as 0.005 cm deep by 0.254 cm long by 0.005 cm wide have been detected on outside diameter surfaces of a 1.43 cm outside diameter fuel rod cladding with a 0.094 cm wall thickness and 0.010 cm deep by 0.254 cm long by 0.005 cm wide on the inside diameter surface

  10. Shell Inspection History and Current CMM Inspection Efforts

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-01-26

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

  11. 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.

  12. 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.

  13. A probe for Eddy current inspection devices

    International Nuclear Information System (INIS)

    1974-01-01

    The invention relates to a surface probe for Eddy current inspection devices. According to the invention, said probe comprises two magnetic core windings, with their axes in parallel relationship and at right angles to the surface of the part to be inspected. This can be applied to the nondestructive inspection of reactor components [fr

  14. 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 ...

  15. 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

  16. Eddy current inspection of tubing

    International Nuclear Information System (INIS)

    Bauza, J. L. R.; Herrero, J.; Diaz, J.

    1966-01-01

    The Experimental research work carried out to develop a Eddy current testing equipment is described. Search coils with ferrite or air cores were used and the obtained results are discussed. Valuable information was gained from a improved channel in which a direct measure of the defect and the reference signal phase difference is obtained. Artificial defect used to evaluate resolution and sensitivity were produced by electro-machining and mechanical means. Finned SAP tubing was tested in a routine basis with the described equipment and the results plotted. Basic and theoretical considerations on the Eddy current testing technique are given in the last section of this report. (Author)

  17. Performance demonstration requirements for eddy current steam generator tube inspection

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Heasler, P.G.; Anderson, C.M.

    1992-10-01

    This paper describes the methodology used for developing performance demonstration tests for steam generator tube eddy current (ET) inspection systems. The methodology is based on statistical design principles. Implementation of a performance demonstration test based on these design principles will help to ensure that field inspection systems have a high probability of detecting and correctly sizing tube degradation. The technical basis for the ET system performance thresholds is presented. Probability of detection and flaw sizing tests are described

  18. Eddy current inspection of mildly ferromagnetic tubing

    International Nuclear Information System (INIS)

    Mayo, W.R.; Carter, J.R.

    1984-02-01

    The past decade has seen the development of eddy current probes for inspection of the mildly ferro-magnetic alloy Monel 400. Due to the rapid advances in permanent magnet technology similar probes have been upgraded to magnetically saturate, and hence inspect, the duplex stainless steel Sandvik 3RE60, which has saturation induction more than twice that of Monel 400. Prototypes of these probes have been tested in three ways: saturation capability, quality of typical eddy current data, and ability to eliminate permeability induced signals. Successful laboratory testing, potential applications, and limitations of these type probes are discussed

  19. 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

  20. Eddy current inspection of stationary blade rings

    International Nuclear Information System (INIS)

    Krzywosz, K.J.; Hastings, S.N.

    1994-01-01

    Stationary turbine blade rings in a US power plant have experienced chloride-induced cracking. Failure analysis determined two types of cracking mechanisms: corrosion fatigue cracking confined to the leading edge of the outer shroud; and stress corrosion cracking present all over the blade surface. Fluorescent dye penetrant is typically used to detect and size cracks. However, it requires cleaning the blade rings by sandblasting to obtain reliable inspection results. Sand blasting in turn requires sealing the lower half of the turbine housing to prevent sand from contaminating the rest of the power plant components. Furthermore, both the penetrant examination and the removal of the sand are time consuming and costly. An alternative NDE technique is desirable which requires no pre-cleaning of the blade and a quick go/no-go inspection with the capability of estimating the crack length. This paper presents an innovative eddy current technique which meets the desired objectives by incorporating the use of specially designed contoured scanners equipped with an array of pancake coils. A set of eddy current pancake coils housed in three different scanners is used to manually scan and inspect the convex side of the stationary blade rings. The pancake coils are operated in a transmit/receive mode using two separate eddy current instruments. This paper presents the inspection concept, including scanner and probe designs, and test results from the various stages of multiple blade rings

  1. 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

  2. Experimental modeling of eddy current inspection capabilities

    International Nuclear Information System (INIS)

    Junker, W.R.; Clark, W.G.

    1984-01-01

    This chapter examines the experimental modeling of eddy current inspection capabilities based upon the use of liquid mercury samples designed to represent metal components containing discontinuities. A brief summary of past work with mercury modeling and a detailed discussion of recent experiments designed to further evaluate the technique are presented. The main disadvantages of the mercury modeling concept are that mercury is toxic and must be handled carefully, liquid mercury can only be used to represent nonferromagnetic materials, and wetting and meniscus problems can distort the effective size of artificial discontinuities. Artificial discontinuities placed in a liquid mercury sample can be used to represent discontinuities in solid metallic structures. Discontinuity size and type cannot be characterized from phase angle and signal amplitude data developed with a surface scanning, pancake-type eddy current probe. It is concluded that the mercury model approach can greatly enhance the overall understanding and applicability of eddy current inspection techniques

  3. 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

  4. Current status of automated ultrasonic pipe inspection systems - ISI of stainless steel piping systems in BWR power plants

    International Nuclear Information System (INIS)

    Jeong, P.

    1985-01-01

    The field of ultrasonics nondestructive testing is constantly expanding its ability of acquiring data and its speed by implementing a computer into the testing system. The computer made it possible to store massive test data into a compact magnetic hard disk for permanent records. The data outputs are displayed on the color CRT screen, and varieties of image display methods, such as A-scan, B-scan, C-scan, P-scan, or many other 3 dimensional isometric views and the modified display techniques are available to an operator. Various hardcopy machines are now a part of the testing system so that the displayed data outputs can be easily copied and filed for permanent documentation. The faster and more accurate mechanized scanners are gradually being substituted for the conventional manual scanning method which has been a major time consuming part of the testing operation. When all such improvements are combined into an integral unit, a reliable, fully automated ultrasonic testing system can by made. The fully automated ultrasonic testing system is needed not only for fast data acquisition, processing, and reliable data display, but also, even more importantly, for considerable reduction of human intervention, which could be a critical factor under the severely limited field environment. Obviously, in the past several years, tremendous accomplishments have been made in automating the test system, and many such systems are being used in the field. However, most of the existing automated systems are still bulky in size and the displayed data is often difficult to interpret to the field operators. Major effect should, therefore, be directed to size reduction of the system as well as improvement on the system reliability

  5. Eddy current inspection of steam generator tubing plugs

    International Nuclear Information System (INIS)

    Cullen, W.K.

    1990-01-01

    In response to the issues raised regarding the integrity of nuclear steam generator tubing plugs manufactured from certain heats of Inconel 600, Westinghouse engineers have developed, qualified and implemented an eddy current inspection system for the in-place assessment of these plugs. The heart of the system is a robotic and effector which delivers an eddy current sensor through the reduced diameter of the plug expander and actuates the coil to physical contact with the expanded inside bore of the plug. Once deployed, the eddy current sensor is rotated along a helical path to produce a detailed scan of the plug surface above the final position of the expander. This testing produces an isometric display of degradation due to primary water stress corrosion cracking, on the inside surface of the plug. To date, successful inspections have been conducted at two nuclear units with two different robotic delivery systems. While designed specifically for mechanical plugs with a bottle bore cavity, the inspection system can also be used for expanded straight bore plugs. Details of the inspection system along with a discussion of qualification activities and actual field results are presented in this paper

  6. Surface inspection technique with an eddy current testing array probe

    International Nuclear Information System (INIS)

    Nishimizu, Akira; Endo, Hisashi; Tooma, Masahiro; Otani, Kenichi; Ouchi, Hirofumi; Yoshida, Isao; Nonaka, Yoshio

    2010-01-01

    An eddy current testing (ECT) system has been developed for inspecting weld surfaces of components in the reactor pressure vessel of nuclear plants. The system can be applied to curved surfaces with an ECT array probe, it can discriminate flaws from other signal factors by using a combination of arrayed coils signal-phase. The system is applied to a mock-up of core internal components and the signal discrimination using the signal-phase clearly separated flaw and noise signals. (author)

  7. Essential parameters in eddy current inspection

    International Nuclear Information System (INIS)

    Stepinski, T.

    2000-05-01

    Our aim was to qualitatively analyze a number of variables that may affect the result of eddy current (EC) inspection but because of various reasons are not considered as essential in common practice. In the report we concentrate on such variables that can vary during or between inspections but their influence is not determined during routine calibrations. We present a qualitative analysis of the influence of the above-mentioned variables on the ability to detect and size flaws using mechanized eddy current testing (ET). ET employs some type of coil or probe, sensing magnetic flux generated by eddy currents induced in the tested specimen. An amplitude-phase modulated signal (with test frequency f0 ) from the probe is sensed by the EC instrument. The amplitude-phase modulated signal is amplified and demodulated in phase-sensitive detectors removing carrier frequency f0 from the signal. The detectors produce an in-phase and a quadrature component of the signal defining it as a point in the impedance plane. Modern instruments are provided with a screen presenting the demodulated and filtered signal in complex plane. We focus on such issues, related to the EC equipment as, probe matching, distortion introduced by phase discriminators and signal filters, and the influence of probe resolution and lift-off on sizing. The influence of different variables is investigated by means of physical reasoning employing theoretical models and demonstrated using simulated and real EC signals. In conclusion, we discuss the way in which the investigated variables may affect the result of ET. We also present a number of practical recommendations for the users of ET and indicate the areas that are to be further analyzed

  8. 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.

  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. 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

  12. Apparatus For Eddy-Current Inspection Of Bolts

    Science.gov (United States)

    Amos, Jay M.

    1994-01-01

    Eddy-current apparatus for inspection of bolts, studs, and other threaded fasteners detects flaws in threads, shanks, and head fillets. With help of apparatus, technician quickly inspects fasteners of various dimensions. Accommodates fasteners with diameters from 0.190 in. to 1 in. and with lengths up to 5 in. Basic design modified to accommodate fasteners of other sizes.

  13. Eddy current inspection on heat exchanger tubes - problems and limitations

    International Nuclear Information System (INIS)

    Ilham Mukriz; Zainal Abidin Mohamed; Hairul Hasmoni Khairul Anuar; Mohd Salleh; Mahmood Dollah

    2005-01-01

    This paper focus on problems associated to eddy current inspection of heat exchanger tubes. A brief review on heat exchanger design and operation is presented. Eddy current technique in identifying inhomogeneity in tested tubes is discussed, highlighting its limitation in distinguishing between real pit type defects and other mundane anomalies. The limitation of the eddy current probe and equipment pertinent to the inspection are identified and areas of improvement are discussed. (Author)

  14. 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

  15. 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

  16. 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)

  17. 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

  18. 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.

  19. Problems and limitations of eddy current tube inspection

    International Nuclear Information System (INIS)

    Ilham Mukriz Zainal Abidin; Khairul Anuar Mohd Salleh; Mohamed Hairul Hasmoni

    2003-01-01

    Incomplete appreciation of eddy current limitations has contributed to both under-utilization and misapplication of the technique. A brief review on the physical principle of eddy current is presented. Eddy current technique in identifying inhomogeneity in tested tubes is discussed, highlighting its limitation in distinguishing between real pit type defects and other mundane anomalies. The variables responsible for limitation in eddy current tube inspection are discussed and alternative approaches, where they exist, are suggested. (Author)

  20. Inspection of cup-shaped steel parts from the I.D. side using eddy current

    Science.gov (United States)

    Griffiths, Erick W.; Pearson, Lee H.

    2018-04-01

    An eddy current method was developed to inspect cup-shaped steel parts from the I.D. side. During the manufacturing process of these parts, a thin Al tape foil is applied to the I.D. side of the part. One of the critical process parameters is that only one foil layer can be applied. An eddy current inspection system was developed to reject parts with more than one foil layer. The Al tape foil is cut to length to fit the inner diameter, however, after application of the foil there is a gap created between the beginning and end of the foil. It was found that this gap interfered with the eddy current inspection causing a false positive indication. To solve this problem a sensor design and data analysis process were developed to overcome the effects of these gaps. The developed system incorporates simultaneous measurements from multiple eddy current sensors and signal processing to achieve a reliable inspection.

  1. 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.

  2. 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.)

  3. Performance trial experience with Danieli new-generation eddy-current surface inspection system for wire rod mill: the equipment and the results at TRM, Rotherham, England

    International Nuclear Information System (INIS)

    Battistutto, R.

    1999-01-01

    Production flexibility and product quality are key subjects that can significantly influence the competitiveness of a steel-making company; recently, they can even affect its profitable permanence on the market. Danieli Automation, thanks to 25-year experience in automation systems for the rolling mill, can offer their customers effective products and solutions specifically designed and developed for total control on the finished product quality. This target is achieved by optimization of yield, availability of the installations and use of the human resources. Results of the above experience and development is the IIITEST instrumentation product family for in-line surface inspection quality control. (author)

  4. Magnetic Particle inspection by DC and AC magnetization current

    International Nuclear Information System (INIS)

    Lim, Zhong Soo; Kim, Goo Hwa

    1996-01-01

    Dry magnetic particle inspection was performed to detect the surface defects of the steel billets. The detectability was evaluated according to magnetizing current, temperature, and amount of the magnetic particles on material. We selected a certain set of steel compositions for target materials. Their magnetic properties are measured with B-H hysteresis graph. Results of the magnetic particle inspection(MPI) by direct magnetizing current was compared with results of the finite element method calculations, which were verified by measurement of the magnetic leakage flux above the surface of material. For square rod materials, the magnetic flux density at the corner was about 30% of that at the face center with sufficiently large direct magnetizing current, while it is about 70% with alternating magnetizing current. Alternating magnetizing current generates rather uniform magnetic flux density running from the center to the corner except for the region of about 10 mm extending from the corner.

  5. 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

  6. 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.

  7. 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

  8. Current food chain information provides insufficient information for modern meat inspection of pigs.

    Science.gov (United States)

    Felin, Elina; Jukola, Elias; Raulo, Saara; Heinonen, Jaakko; Fredriksson-Ahomaa, Maria

    2016-05-01

    Meat inspection now incorporates a more risk-based approach for protecting human health against meat-borne biological hazards. Official post-mortem meat inspection of pigs has shifted to visual meat inspection. The official veterinarian decides on additional post-mortem inspection procedures, such as incisions and palpations. The decision is based on declarations in the food chain information (FCI), ante-mortem inspection and post-mortem inspection. However, a smooth slaughter and inspection process is essential. Therefore, one should be able to assess prior to slaughter which pigs are suitable for visual meat inspection only, and which need more profound inspection procedures. This study evaluates the usability of the FCI provided by pig producers and considered the possibility for risk ranking of incoming slaughter batches according to the previous meat inspection data and the current FCI. Eighty-five slaughter batches comprising 8954 fattening pigs were randomly selected at a slaughterhouse that receives animals from across Finland. The mortality rate, the FCI and the meat inspection results for each batch were obtained. The current FCI alone provided insufficient and inaccurate information for risk ranking purposes for meat inspection. The partial condemnation rate for a batch was best predicted by the partial condemnation rate calculated for all the pigs sent for slaughter from the same holding in the previous year (p<0.001) and by prior information on cough declared in the current FCI (p=0.02) statement. Training and information to producers are needed to make the FCI reporting procedures more accurate. Historical meat inspection data on pigs slaughtered from the same holdings and well-chosen symptoms/signs for reporting, should be included in the FCI to facilitate the allocation of pigs for visual inspection. The introduced simple scoring system can be easily used for additional information for directing batches to appropriate meat inspection procedures. To

  9. 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.

  10. 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)

  11. 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.

  12. 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

  13. 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)

  14. Validating eddy current array probes for inspecting steam generator tubes

    International Nuclear Information System (INIS)

    Sullivan, S.P.; Cecco, V.S.; Obrutsky, L.S.

    1997-01-01

    A CANDU nuclear reactor was shut down for over one year because steam generator (SG) tubes had failed with outer diameter stress-corrosion cracking (ODSCC) in the U-bend section. Novel, single-pass eddy current transmit-receive probes, denoted as C3, were successful in detecting all significant cracks so that the cracked tubes could be plugged and the unit restarted. Significant numbers of tubes with SCC were removed from a SG in order to validate the results of the new probe. Results from metallurgical examinations were used to obtain probability-of-detection (POD) and sizing accuracy plots to quantify the performance of this new inspection technique. Though effective, the above approach of relying on tubes removed from a reactor is expensive, in terms of both economic and radiation-exposure costs. This led to a search for more affordable methods to validate inspection techniques and procedures. Methods are presented for calculating POD curves based on signal-to-noise studies using field data. Results of eddy current scans of tubes with laboratory-induced ODSCC are presented with associated POD curves. These studies appear promising in predicting realistic POD curves for new inspection technologies. They are being used to qualify an improved eddy current array probe in preparation for field use. (author)

  15. 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

  16. Current deflection NDE for pipeline inspection and monitoring

    Science.gov (United States)

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

    2016-02-01

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

  17. 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

  18. 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

  19. Advances based on digital technology named TEDDY+ for inspection of eddy current

    International Nuclear Information System (INIS)

    Barcenilla, V.; Hernandez, J.; Ribes, B.

    2007-01-01

    As a result of the recent developing line of eddy current data acquisition system a new product based on digital technology named TEDDY+, comes to the market. With only 4 kg of weight constitutes a great advance with regards to other equipment's available in the market. These advances, have enabled, among others, to increase considerably the signal to noise (S/N) ratio, avoid typical saturation problems in the eddy current signal, increase the inspection speed, eliminate the reference probe, detect the air/tube signal in real time, and the possibility to integrate the tester inside a push puller thanks to its reduced size and to have integrated as part of the ET equipment the mechanical systems control board. Two product lines have been developed, one oriented to any market and application (nuclear market, industrial and aeronautical, chemical and petrochemical, etc) and other specially dedicated to the massive inspection of tubes, named TEDDY+SP (Suitcase Pusher). Both lines are prepared to use eddy current arrays which clearly constitute the future of the eddy current inspection systems. The new TEDDY+ line of products presented in this paper constitutes one of the most powerful and reliable existing in the market. These improvements and novelties place the new ET inspection system from Tecnatom as one of the most powerful and reliable in the market. (Author)

  20. 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.

  1. Performance demonstration tests for eddy current inspection of steam generator tubing

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Heasler, P.G.; Anderson, C.M.

    1996-05-01

    This report describes the methodology and results for development of performance demonstration tests for eddy current (ET) inspection of steam generator tubes. Statistical test design principles were used to develop the performance demonstration tests. Thresholds on ET system inspection performance were selected to ensure that field inspection systems would have a high probability of detecting and and correctly sizing tube degradation. The technical basis for the ET system performance thresholds is presented in detail. Statistical test design calculations for probability of detection and flaw sizing tests are described. A recommended performance demonstration test based on the design calculations is presented. A computer program for grading the probability of detection portion of the performance demonstration test is given

  2. Performance demonstration tests for eddy current inspection of steam generator tubing

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, R.J.; Heasler, P.G.; Anderson, C.M.

    1996-05-01

    This report describes the methodology and results for development of performance demonstration tests for eddy current (ET) inspection of steam generator tubes. Statistical test design principles were used to develop the performance demonstration tests. Thresholds on ET system inspection performance were selected to ensure that field inspection systems would have a high probability of detecting and and correctly sizing tube degradation. The technical basis for the ET system performance thresholds is presented in detail. Statistical test design calculations for probability of detection and flaw sizing tests are described. A recommended performance demonstration test based on the design calculations is presented. A computer program for grading the probability of detection portion of the performance demonstration test is given.

  3. 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)

  4. 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.

  5. 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)

  6. 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....

  7. 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

  8. 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

  9. 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.

  10. 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)

  11. An application of the eddy-current method for inspections of austenitic cladding

    International Nuclear Information System (INIS)

    Kubis, S.; Herka, M.; Krajcovic, R.

    1999-01-01

    The application of the eddy-current method for inspections of austenitic cladding by means of pancake probes. Phase and amplitude characteristics of artificial defects and anticipated interference signals. Optimization of inspection parameters

  12. 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

  13. 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

  14. Eddy current inspection of weld defects in tubing

    Science.gov (United States)

    Katragadda, G.; Lord, W.

    1992-01-01

    An approach using differential probes for the inspection of weld defects in tubing is studied. Finite element analysis is used to model the weld regions and defects. Impedance plane signals are predicted for different weld defect types and compared wherever possible with signals from actual welds in tubing. Results show that detection and sizing of defects in tubing is possible using differential eddy current techniques. The phase angle of the impedance plane trajectory gives a good indication of the sizing of the crack. Data on the type of defect can be obtained from the shape of the impedance plane trajectory and the phase. Depending on the skin depth, detection of outer wall, inner wall, and subsurface defects is possible.

  15. Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

    International Nuclear Information System (INIS)

    Scott Hower; Luiza Vladu; Adrian Nichisov; Mihai Cretu

    2006-01-01

    Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

  16. 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.

  17. 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

  18. Space Shuttle Program (SSP) Orbiter Main Propulsion System (MPS) Gaseous Hydrogen (GH2) Flow Control Valve (FCV) Poppet Eddy Current (EC) Inspection Probability of Detection (POD) Study. Volume 1

    Science.gov (United States)

    Piascik, Robert S.; Prosser, William H.

    2011-01-01

    The Director of the NASA Engineering and Safety Center (NESC), requested an independent assessment of the anomalous gaseous hydrogen (GH2) flow incident on the Space Shuttle Program (SSP) Orbiter Vehicle (OV)-105 during the Space Transportation System (STS)-126 mission. The main propulsion system (MPS) engine #2 GH2 flow control valve (FCV) LV-57 transition from low towards high flow position without being commanded. Post-flight examination revealed that the FCV LV-57 poppet had experienced a fatigue failure that liberated a section of the poppet flange. The NESC assessment provided a peer review of the computational fluid dynamics (CFD), stress analysis, and impact testing. A probability of detection (POD) study was requested by the SSP Orbiter Project for the eddy current (EC) nondestructive evaluation (NDE) techniques that were developed to inspect the flight FCV poppets. This report contains the findings and recommendations from the NESC assessment.

  19. Space Shuttle Program (SSP) Orbiter Main Propulsion System (MPS) Gaseous Hydrogen (GH2) Flow Control Valve (FCV) Poppet Eddy Current (EC) Inspection Probability of Detection (POD) Study. Volume 2; Appendices

    Science.gov (United States)

    Piascik, Robert S.; Prosser, William H.

    2011-01-01

    The Director of the NASA Engineering and Safety Center (NESC), requested an independent assessment of the anomalous gaseous hydrogen (GH2) flow incident on the Space Shuttle Program (SSP) Orbiter Vehicle (OV)-105 during the Space Transportation System (STS)-126 mission. The main propulsion system (MPS) engine #2 GH2 flow control valve (FCV) LV-57 transition from low towards high flow position without being commanded. Post-flight examination revealed that the FCV LV-57 poppet had experienced a fatigue failure that liberated a section of the poppet flange. The NESC assessment provided a peer review of the computational fluid dynamics (CFD), stress analysis, and impact testing. A probability of detection (POD) study was requested by the SSP Orbiter Project for the eddy current (EC) nondestructive evaluation (NDE) techniques that were developed to inspect the flight FCV poppets. This report contains the Appendices to the main report.

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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)

  5. 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...

  6. 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.

  7. 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)

  8. 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.

  9. 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...

  10. 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

  11. 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.

  12. 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

  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. Evaluation of the eddy-current method for the inspection of steam generator tubing: denting

    International Nuclear Information System (INIS)

    Brown, S.D.; Flora, J.H.

    1977-01-01

    Continued evaluation of existing eddy-current in-service inspection (ISI) methods for steam generator tubing has emphasized the effects of denting. Denting is a circumferential deformation of the tube in the support region as a result of the formation of a magnetite, Fe 3 O 4 , corrosion product on the carbon steel tube support plate in the crevice between the support plate and the tube wall. The effects of denting on eddy current inspection are twofold: (1) The detection and measurement of defects in the dented region is hampered by the distortion of the eddy-current response signals caused by the dents and (2) large dents may prevent the passage of high fill factor probes forcing the inspection teams to use a smaller probe in undented regions. Unless appropriate measures are taken, less reliable detection of defects and estimation of their depth can result. The report presents an experimental evaluation of existing eddy-current ISI methods when used to inspect dented regions. Tubes were mechanically dented to simulate various degrees of service induced denting. These tubes were then inserted in carbon steel tube support plates and the crevice region between the support plate and tube was subsequently packed with powdered magnetite. Diametral dent sizes considered during this program varied between 1 and 10 mils. Eddy-current signal patterns and strip chart recordings were obtained using a variety of test parameters, such as frequency, phase rotation and coil configuration, on tube samples containing various degrees of denting and with several types of defects in the dented system

  15. 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

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. 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.

  1. 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)

  2. 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

  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. 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)

  6. 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

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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...

  12. 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...

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. A Steel Ball Surface Quality Inspection Method Based on a Circumferential Eddy Current Array Sensor.

    Science.gov (United States)

    Zhang, Huayu; Xie, Fengqin; Cao, Maoyong; Zhong, Mingming

    2017-07-01

    To efficiently inspect surface defects on steel ball bearings, a new method based on a circumferential eddy current array (CECA) sensor was proposed here. The best probe configuration, in terms of the coil quality factor (Q-factor), magnetic field intensity, and induced eddy current density on the surface of a sample steel ball, was determined using 3-, 4-, 5-, and 6-coil probes, for analysis and comparison. The optimal lift-off from the measured steel ball, the number of probe coils, and the frequency of excitation current suitable for steel ball inspection were obtained. Using the resulting CECA sensor to inspect 46,126 steel balls showed a miss rate of ~0.02%. The sensor was inspected for surface defects as small as 0.05 mm in width and 0.1 mm in depth.

  1. A Steel Ball Surface Quality Inspection Method Based on a Circumferential Eddy Current Array Sensor

    Directory of Open Access Journals (Sweden)

    Huayu Zhang

    2017-07-01

    Full Text Available To efficiently inspect surface defects on steel ball bearings, a new method based on a circumferential eddy current array (CECA sensor was proposed here. The best probe configuration, in terms of the coil quality factor (Q-factor, magnetic field intensity, and induced eddy current density on the surface of a sample steel ball, was determined using 3-, 4-, 5-, and 6-coil probes, for analysis and comparison. The optimal lift-off from the measured steel ball, the number of probe coils, and the frequency of excitation current suitable for steel ball inspection were obtained. Using the resulting CECA sensor to inspect 46,126 steel balls showed a miss rate of ~0.02%. The sensor was inspected for surface defects as small as 0.05 mm in width and 0.1 mm in depth.

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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

  7. Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Obrutsky, L.; Mendonca, H.

    1986-01-01

    In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

  8. Current state and development trends of inspections of steam generator tubes by eddy currents method

    International Nuclear Information System (INIS)

    Kubis, S.; Herman, M.

    1988-01-01

    The requirements are presented for steam generator tube testing and the factors are discussed affecting the accuracy of measurement by the eddy currents method. The individual types of the eddy currents method are described, such as the single-frequency method, the multi-frequency method and the pulse eddy currents method. The demands are summed up on manipulator systems whose design is adapted to the steam generator configuration conditions. (E.S.). 5 figs., 16 possu

  9. 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)

  10. 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

  11. 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)

  12. 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...

  13. 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)

  14. 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

  15. Eddy current and ultrasonic fuel channel inspection at Karachi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Mayo, W.R.; Alam, M.M.

    1997-01-01

    In November of 1993 and in-service inspection was performed on eight fuel channels in the Karachi Nuclear Power Plant (KANUPP) reactor. The workscope included ultrasonic and eddy current volumetric examinations, and eddy current measurement of pressure-to calandria tube gap. This paper briefly discusses the planning strategy of the ultrasonic and eddy current examinations, and describes the equipment developed to meet the requirements, followed by details of the actual channel inspection campaign. The presented nondestructive examinations assisted in determining fitness for service of KANUPP reactor channels in general, and confirmed that the problems associated with channel G12 were not generic in nature. (author)

  16. Eddy Currents Inspection of CANDU Steam Generator Tubes using Zetec's ZR-1 Robot. Experience in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Scott Hower [Zetec Inc. (Romania); Luiza Vladu; Adrian Nichisov; Mihai Cretu [COMPCONTROL ING. (Romania)

    2006-07-01

    Full text of publication follows: The commercial operation of Unit 1 of Cernavoda NPP started on 2 December, 1996. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium. The nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant has four CANDU - design steam generators that have been in service since 1996. The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience - based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of tool heads ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, light weight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The unit's reactor type is PHWR-CANDU 6 (electrical capacity 706 MWe), using natural uranium; the nuclear fuel is manufactured in Romania. The Cernavoda nuclear power plant Unit 1 has four CANDU - design steam generators that have been in service since 1996. The paper presents also the Zetec's field experience and customer experience with this system. It describes the equipment setup in Cernavoda's steam generators mock-up, functional tests and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (authors)

  17. 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.

  18. The TS 600: automatic control system for eddy currents

    International Nuclear Information System (INIS)

    Poulet, J.P.

    1986-10-01

    In the scope of fabrication and in service inspection of the PWR steam generator tubing bendle, FRAMATOME developed an automatic Eddy Current testing system: TS600. Based on a mini-computer, TS600 allows to digitize, to store and to process data in various ways, so it is possible to perform several kinds of inspection: conventional inservice inspection, roll area profilometry...... TS600 can also be used to develop new methods of examination [fr

  19. 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

  20. 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.

  1. Motion-induced eddy current thermography for high-speed inspection

    Directory of Open Access Journals (Sweden)

    Jianbo Wu

    2017-08-01

    Full Text Available This letter proposes a novel motion-induced eddy current based thermography (MIECT for high-speed inspection. In contrast to conventional eddy current thermography (ECT based on a time-varying magnetic field created by an AC coil, the motion-induced eddy current is induced by the relative motion between magnetic field and inspected objects. A rotating magnetic field created by three-phase windings is used to investigate the heating principle and feasibility of the proposed method. Firstly, based on Faraday’s law the distribution of MIEC is investigated, which is then validated by numerical simulation. Further, experimental studies are conducted to validate the proposed method by creating rotating magnetic fields at different speeds from 600 rpm to 6000 rpm, and it is verified that rotating speed will increase MIEC intensity and thereafter improve the heating efficiency. The conclusion can be preliminarily drawn that the proposed MIECT is a platform suitable for high-speed inspection.

  2. 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.)

  3. Evaluation and field validation of Eddy-Current array probes for steam generator tube inspection

    International Nuclear Information System (INIS)

    Dodd, C.V.; Pate, J.R.

    1996-07-01

    The objective of the Improved Eddy-Current ISI for Steam Generator Tubing program is to upgrade and validate eddy-current inspections, including probes, instrumentation, and data processing techniques for inservice inspection of new, used, and repaired steam generator tubes; to improve defect detection, classification, and characterization as affected by diameter and thickness variations, denting, probe wobble, tube sheet, tube supports, copper and sludge deposits, even when defect types and other variables occur in combination; to transfer this advanced technology to NRC's mobile NDE laboratory and staff. This report describes the design of specialized high-speed 16-coil eddy-current array probes. Both pancake and reflection coils are considered. Test results from inspections using the probes in working steam generators are given. Computer programs developed for probe calculations are also supplied

  4. 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%.

  5. 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)

  6. 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

  7. Improved eddy-current inspection for steam generator tubing

    International Nuclear Information System (INIS)

    Dodd, C.V.; Pate, J.R.; Allen, J.D. Jr.

    1989-01-01

    Computer programs have been written to allow the analysis of different types of eddy-current probes and their performance under different steam generator test conditions. The probe types include the differential bobbin probe, the absolute bobbin probe, the pancake probe and the reflection probe. The generator test conditions include tube supports, copper deposits, magnetite deposits, denting, wastage, pitting, cracking and IGA. These studies are based mostly on computed values, with the limited number of test specimens available used to verify the computed results. The instrument readings were computed for a complete matrix of the different test conditions, and then the test conditions determined as a function of the readings by a least-squares technique. A comparison was made of the errors in fit and instrument drift for the different probe types. The computations of the change in instrument reading due to the defects have led to an ''inversion'' technique in which the defect properties can be computed from the instrument readings. This has been done both experimentally and analytically for each of these probe types. 3 refs., 13 figs., 1 tab

  8. 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.

  9. 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

  10. Eddy-current inspection of high flux isotope reactor nuclear control rods

    International Nuclear Information System (INIS)

    Smith, J.H.; Chitwood, L.D.

    1981-07-01

    Inner control rods for the High Flux Isotope Reactor were nondestructively inspected for defects by eddy-current techniques. During these examinations aluminum cladding thickness and oxide thickness on the cladding were also measured. Special application techniques were required because of the high-radiation levels (approx. 10 5 R/h at 30 cm) present and the relatively large temperature gradients that occurred on the surface of the control rods. The techniques used to perform the eddy-current inspections and the methods used to reduce the associated data are described

  11. 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...

  12. CURRENT TRANSFER SYSTEMS

    Science.gov (United States)

    Watt, D.A.

    1956-07-01

    A current transfer system is described for transferring current between a rotating member and a co-axial stationary member. The particular area of application for the invention is in connection with homopolar generators where a low voltage and high current are generated. The current tramsfer system of the invention comprises a rotor member and a co-axial stator member wherein one of the members is shaped to provide a circumferential surface concave in section and the other member is shaped to have a peripheral portion in close proximity to the surface, whereby a liquid metal can be stably supported between the two members when they are moving relative to one another to establish an electrical conducting path between the members.

  13. Eddy current automatic inspection of heat exchangers in nuclear power stations

    International Nuclear Information System (INIS)

    Cazal, M.; Scopelliti, J.D.; Mendez, J.

    1997-01-01

    This presentation describes the eddy current tube inspection techniques for heavy heat exchangers in nuclear power stations. The purpose of these eddy current tests, is first to determine the integrity of the heat exchanger tubes, and to characterize the related types of defects in each case following to their analysis and cause determination and subsequent inspection planning. This task requires a group highly qualified personnel with high tech automate equipment. The organization of the group required a correct function and task assignment in order to achieve efficiency in scheduling, with simultaneous inspection to different components in a continuous base and uninterruptedly. A lead specialist is in charge of the group, which is set up by several shift supervisors, a qualified tele manipulator installation crew a number of qualified tele manipulator operators, and the specialist for data acquisition and certified eddy current signal evaluators plus some other support technicians and administrations helpers. In order to comply with inspection requirements, a bunch of technical procedures had to be developed. The following equipment is available nowadays: Zetec SM-13, SM-23 and SM-22 tele manipulators for inspection probes positioning, with different shapes and configuration (rotating probes, flexible probes for U-Bends, and magnetic saturation probes endowed with their own driving units) and remote data acquisition units identified as MIZ-18 A and MIZ-30, which are remotely operated from a mobile lab installed in a trailer, outside the reactor building. The available equipment allows a simultaneous inspection of three different plant components (two steam generators and a moderator heat exchanger). We are also in a position of performing eddy current tube inspection in more than a NSP at the same time. The Zetec Eddynet software is used in the manipulator operation and for the data acquisition and defect evaluation. This software operates within Windows

  14. 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

  15. 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

  16. 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

  17. 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...

  18. 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

  19. 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

  20. 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

  1. 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...

  2. 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.)

  3. 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)

  4. 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

  5. Challenges associated with the current processes for ultrasonic inspection of CANDU reactor feeder piping

    Energy Technology Data Exchange (ETDEWEB)

    Machowski, C. [Babcock & Wilcox Canada Ltd., Cambridge, Ontario (Canada)

    2012-07-01

    CANDU® PHT Feeder Piping is generally constructed from SA106 Grade B carbon steel, which is known to be susceptible to flow accelerated corrosion when exposed to certain environmental conditions. The configuration of the CANDU reactor promotes thinning of the inside surface of the pipe walls, predominantly at the outlet feeders. Inspection of this piping is currently conducted using ultrasonic techniques and is governed by the requirements established by the CANDU Owners Group (COG). There are many challenges associated with these inspections as a result of the complexity of the reactor piping configuration. Geometrical anomalies on the surface of the pipe and non-circular geometries at the tight radius bends hinder the performance of conventional ultrasonic techniques. This can cause lost signals in areas of interest, which in turn often results in rework in order to satisfy the inspection requirements and justify fitness for service of these components. There are also many inspection sites which have limited access due to physical restrictions on the reactor face; therefore in order to maximize the performance of an inspection campaign, it is paramount that the inspection personnel and the inspection technology be well integrated through training simulations prior to execution. These inspection challenges increase the complexity of the analysis process as ultrasonic signals get distorted and lost as a result of non-circular pipe geometries. In order to ensure a high level of integrity in the analysis results, a conservative process is utilized in which two analysts independently examine the data, and a third analyst reviews their results and submits the final call. A Data Management Software application (DMS) is used to input and store the three analysis results. Another important function of the DMS is to provide a communication link between the different work-groups associated with the inspection activities. The focus of this presentation discusses:

  6. Eddy current technology for heat exchanger and steam generator tube inspection

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  7. Eddy current technology for heat exchanger and steam generator tube inspection

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  8. 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

  9. 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

  10. 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.

  11. 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

  12. Evaluation of the eddy-current method of inspecting steam generator tubing

    International Nuclear Information System (INIS)

    Flora, J.H.; Brown, S.D.; Weeks, J.R.

    1976-01-01

    The objective of this project has been to evaluate the eddy-current method of inspecting steam generator tubing by conducting a series of laboratory experiments with conventional eddy-current equipment. The experiments have involved obtaining eddy-current measurements on samples of 7/8-inch OD Inconel-600 tubing provided by the Westinghouse Nuclear Energy Systems Division. A variety of machined defects and some chemically induced flaws, such as stress corrosion cracks were fabricated in the tubing. Statistical evaluation of the data was employed to estimate the error encountered in measuring corrosion defects of various depths. It appears that the eddy-current technique can provide a reasonable measure of defect depth under certain conditions. On the other hand, the evaluation indicates that it is difficult to determine the depth of certain types of flaws with reliability and precision. Furthermore, although some defects as shallow as 10 percent of the tube wall could be detected, it was not possible to detect other types of flaws that were less than 40 percent deep even when the tube supports were not near the defects. The difficulty in detecting small volume flaws is attributed to low signal-to-noise ratio. Noise is a result of unwanted signals from test variables, such as wobble and variations in tube properties. The error in measurement of certain types of larger defects is associatedin part with test variables and also with the effects that the geometry of the defect has on the eddy-current signal patterns. The distortions in signal patterns caused by gradual wastage type defects and the poor reproducibility of signal patterns obtained from notches that represent stress corrosion cracks are described. Some developments that will rectify these detection and depth measurement problems are discussed

  13. Applying computer modeling to eddy current signal analysis for steam generator and heat exchanger tube inspections

    International Nuclear Information System (INIS)

    Sullivan, S.P.; Cecco, V.S.; Carter, J.R.; Spanner, M.; McElvanney, M.; Krause, T.W.; Tkaczyk, R.

    2000-01-01

    Licensing requirements for eddy current inspections for nuclear steam generators and heat exchangers are becoming increasingly stringent. The traditional industry-standard method of comparing inspection signals with flaw signals from simple in-line calibration standards is proving to be inadequate. A more complete understanding of eddy current and magnetic field interactions with flaws and other anomalies is required for the industry to generate consistently reliable inspections. Computer modeling is a valuable tool in improving the reliability of eddy current signal analysis. Results from computer modeling are helping inspectors to properly discriminate between real flaw signals and false calls, and improving reliability in flaw sizing. This presentation will discuss complementary eddy current computer modeling techniques such as the Finite Element Method (FEM), Volume Integral Method (VIM), Layer Approximation and other analytic methods. Each of these methods have advantages and limitations. An extension of the Layer Approximation to model eddy current probe responses to ferromagnetic materials will also be presented. Finally examples will be discussed demonstrating how some significant eddy current signal analysis problems have been resolved using appropriate electromagnetic computer modeling tools

  14. 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

  15. 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)

  16. 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...

  17. 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.)

  18. Multifrequency eddy-current inspection of seam weld in steel sheath

    Energy Technology Data Exchange (ETDEWEB)

    Smith, J.H.; Dodd, C.V.; Chitwood, L.D.

    1985-04-01

    Multifrequency eddy-current techniques were used to perform a continuous on-line inspection of the seam weld in the steel jacket for a superconducting cable. The inspection was required to detect both surface and internal weld flaws in the presence of a large, highly conductive central conductor. Raw eddy-current data were recorded on magnetic tape, and test properties such as discontinuity size and weld penetration were determined by mathematically fitting these data to coefficients developed with representative standards. A sophisticated computer-controlled scanning technique was applied, and a unique scanning device was developed to provide full coverage of the weld and heat-affected zone. The techniques used to develop this multifrequency eddy-current examination are described in this report along with the test equipment, test procedures, and computer programs.

  19. Multifrequency eddy-current inspection of seam weld in steel sheath

    International Nuclear Information System (INIS)

    Smith, J.H.; Dodd, C.V.; Chitwood, L.D.

    1985-04-01

    Multifrequency eddy-current techniques were used to perform a continuous on-line inspection of the seam weld in the steel jacket for a superconducting cable. The inspection was required to detect both surface and internal weld flaws in the presence of a large, highly conductive central conductor. Raw eddy-current data were recorded on magnetic tape, and test properties such as discontinuity size and weld penetration were determined by mathematically fitting these data to coefficients developed with representative standards. A sophisticated computer-controlled scanning technique was applied, and a unique scanning device was developed to provide full coverage of the weld and heat-affected zone. The techniques used to develop this multifrequency eddy-current examination are described in this report along with the test equipment, test procedures, and computer programs

  20. Current activities and challenges of the European network for inspection and qualification (ENIQ)

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Oliver [European Commission, Joint Research Centre (JRC), Petten (Netherlands). Institute for Energy and Transport (IET); Martin, Etienne [EDF, St Denis (France). Direction Production Ingenierie; Booler, Russ [AMEC Clean Energy Europe, Warrington (United Kingdom); Zetterwall, Tommy [Swedish Qualification Centre, Taeby (Sweden); Walker, Tony [Rolls-Royce Submarines, Derby (United Kingdom)

    2014-10-15

    This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8{sup th} technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

  1. Current activities and challenges of the European network for inspection and qualification (ENIQ)

    International Nuclear Information System (INIS)

    Martin, Oliver; Martin, Etienne; Zetterwall, Tommy; Walker, Tony

    2014-01-01

    This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8 th technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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

  7. 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.

  8. 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.)

  9. 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

  10. 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

  11. 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

  12. An integrated automatic system for the eddy-current testing of the steam generator tubes

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Choi, Seong Su [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    This research project was focused on automation of steam generator tubes inspection for nuclear power plants. ECT (Eddy Current Testing) inspection process in nuclear power plants is classified into 3 subprocesses such as signal acquisition process, signal evaluation process, and inspection planning and data management process. Having been automated individually, these processes were effectively integrated into an automatic inspection system, which was implemented in HP workstation with expert system developed (author). 25 refs., 80 figs.

  13. An integrated automatic system for the eddy-current testing of the steam generator tubes

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Choi, Seong Su [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    This research project was focused on automation of steam generator tubes inspection for nuclear power plants. ECT (Eddy Current Testing) inspection process in nuclear power plants is classified into 3 subprocesses such as signal acquisition process, signal evaluation process, and inspection planning and data management process. Having been automated individually, these processes were effectively integrated into an automatic inspection system, which was implemented in HP workstation with expert system developed (author). 25 refs., 80 figs.

  14. Integrity assessment of research reactor fuel cladding and material testing using eddy current inspection

    International Nuclear Information System (INIS)

    Alencar, Donizete Anderson de

    2004-01-01

    A methodology to perform the integrity assessment of research reactors nuclear fuels cladding, such as those installed in IPR-Rl (TRIGA) and IEA-R1 (MTR), using nondestructive electromagnetic inspection (eddy current) is presented. This methodology is constituted by: the development of calibration reference standards, specific for each type of fuel; the development of special test probes; the recommendations for the inspection equipment calibration; the construction of voltage based evaluation curves and the inspection procedures developed for the characterization of detected flaws. The test probes development, specially those designed for the inspection of MTR fuels cladding, which present access difficulties due to the narrow gap between fuel plates (2,89 mm for IEAR-R1), constituted a challenge that demanded the introduction of unusual materials and constructive techniques. The operational performance of the developed resources, as well as the special operative characteristics of the test probes, such as their immunity to adjacent fuel plates interference and electrical resistivity changes of the fuels meat are experimentally demonstrated. The practical applicability of the developed methodology is verified in non radioactive environment, using a dummy MTR fuel element model, similar to an IEA-R1 reactor fuel element, produced and installed in IPEN, Sao Paulo. The efficacy of the proposed methodology was verified by the achieved results. (author)

  15. Sizing Performance of the Newly Developed Eddy Current System

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Chan Hee; Lee, Hee Jong; Yoo, Hyun Ju; Moon, Gyoon Young; Lee, Tae Hoon [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)

    2013-10-15

    This paper describes the comparison results of sizing performance for two systems. The KHNP developed a new eddy current testing system for the inspection of steam generator tubing in domestic nuclear power plants. The equivalency assessment of the newly developed system with the EPRI-qualified system was already carried out. In this paper, the comparisons of depth-sizing performance for the artificial flaws between two systems were performed. The results show that the newly developed system is in good agreement with the qualified system. Therefore, it is expected that the newly developed eddy current system can be used for the inspection of steam generator tubing in nuclear power plants. There are some non-destructive examination (NDE) methods for the inspection of components in nuclear power plants, such as ultrasonic, radiographic, eddy current testing, etc. The eddy current testing is widely used for the inspection of steam generator (SG) tubing because it offers a relatively low cost approach for high speed, large scale testing of metallic materials in high pressure and temperature engineering systems. The Korea Hydro and Nuclear Power Co., Ltd. (KHNP) developed an eddy current testing system for the inspection of steam generator tubing in nuclear power plants. This system includes not only hardware but software such as the frequency generator and data acquisition-analysis program. The foreign eddy current system developed by ZETEC is currently used for the inspection of steam generator tubing in domestic nuclear power plants. The equivalency assessment between two systems was already carried out in accordance with the EPRI steam generator examination guidelines.

  16. Automation of inspection methods for eddy current testing of steam generator tubes

    International Nuclear Information System (INIS)

    Meurgey, P.; Baumaire, A.

    1990-01-01

    Inspection of all the tubes of a steam generator when the reactor is stopped is required for some of these exchangers affected by stress corrosion cracking. Characterization of each crack, in each tube is made possible by the development of software for processing the signals from an eddy current probe. The ESTELLE software allows a rapid increase of tested tubes, more than 80,000 in 1989 [fr

  17. 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

  18. 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.

  19. 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.

  20. 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)

  1. 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.

  2. Eddy currents inspection of CANDU steam generator' tubes using Zetec's ZR-1 Robot: experience in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Hower, S. [Zetec Inc., Quebec, Quebec (Canada); Serban, M. [CNE-Prod U1 Cernavoda (Romania); Vladu, L. [Compcontrol Ing., Bucharest (Romania)

    2006-07-01

    'Full text:' The paper introduces the new ZR-1 Robot System for Inspection and Maintenance/Repair from Zetec that combines the newest state-of-the-art robotics technology with Zetec experience-based innovation to address the needs for inspection and repair of steam generators. The multipurpose ZR-1 can be easily installed to perform the necessary eddy current inspection and remain installed ready for follow-up maintenance and repair. It has superior technical performances and a modular three axis motion of arm that enables 100% coverage of tube sheet. Automated, repeatable, and precise positioning of toolheads, ensures accurate delivery and reducing costly rework and reduces inspection time by 30%. The modular, lightweight, and portable design permits easy assembly and disassembly through small openings and it reduces setup/tear down time by 30%. The first deployment of the new ZR-1 Robot was made in September 2004 at the Cernavoda NPP inspection outage. The Cernavoda plant has four Advanced 600 MW CANDU-design generators that have been in service since 1996. The paper presents also the Zetec's filed experience and customer experience with this system. It describes the equipment setup in Cernavoda's generator mock-up, functional testes and calibration. Finally, provides details on the execution of the inspection, options for standardizing the inspection techniques and conclusions. (author)

  3. 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

  4. 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

  5. Regression analysis of pulsed eddy current signals for inspection of steam generator tube support structures

    International Nuclear Information System (INIS)

    Buck, J.; Underhill, P.R.; Mokros, S.G.; Morelli, J.; Krause, T.W.; Babbar, V.K.; Lepine, B.

    2015-01-01

    Nuclear steam generator (SG) support structure degradation and fouling can result in damage to SG tubes and loss of SG efficiency. Conventional eddy current technology is extensively used to detect cracks, frets at supports and other flaws, but has limited capabilities in the presence of multiple degradation modes or fouling. Pulsed eddy current (PEC) combined with principal components analysis (PCA) and multiple linear regression models was examined for the inspection of support structure degradation and SG tube off-centering with the goal of extending results to include additional degradation modes. (author)

  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. 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.

  8. 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

  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. Current limiter circuit system

    Science.gov (United States)

    Witcher, Joseph Brandon; Bredemann, Michael V.

    2017-09-05

    An apparatus comprising a steady state sensing circuit, a switching circuit, and a detection circuit. The steady state sensing circuit is connected to a first, a second and a third node. The first node is connected to a first device, the second node is connected to a second device, and the steady state sensing circuit causes a scaled current to flow at the third node. The scaled current is proportional to a voltage difference between the first and second node. The switching circuit limits an amount of current that flows between the first and second device. The detection circuit is connected to the third node and the switching circuit. The detection circuit monitors the scaled current at the third node and controls the switching circuit to limit the amount of the current that flows between the first and second device when the scaled current is greater than a desired level.

  14. A pulsed eddy current probe for inspection of support plates from within Alloy-800 steam generator tubes

    International Nuclear Information System (INIS)

    Krause, T. W.; Babbar, V. K.; Underhill, P. R.

    2014-01-01

    Support plate degradation and fouling in nuclear steam generators (SGs) can lead to SG tube corrosion and loss of efficiency. Inspection and monitoring of these conditions can be integrated with preventive maintenance programs, thereby advancing station-life management processes. A prototype pulsed eddy current (PEC) probe, targeting inspection issues associated with SG tubes in SS410 tube support plate structures, has been developed using commercial finite element (FE) software. FE modeling was used to identify appropriate driver and pickup coil configurations for optimum sensitivity to changes in gap and offset for Alloy-800 SG tubes passing through 25 mm thick SS410 support plates. Experimental measurements using a probe that was manufactured based on the modeled configuration, were used to confirm the sensitivity of differential PEC signals to changes in relative position of the tube within the tube support plate holes. Models investigated the effect of shift and tilt of tube with respect to hole centers. Near hole centers and for small shifts, modeled signal amplitudes from the differentially connected coil pairs were observed to change linearly with tube shift. This was in agreement with experimentally measured TEC coil response. The work paves the way for development of a system targeting the inspection and evaluation of support plate structures in steam generators

  15. A pulsed eddy current probe for inspection of support plates from within Alloy-800 steam generator tubes

    Science.gov (United States)

    Krause, T. W.; Babbar, V. K.; Underhill, P. R.

    2014-02-01

    Support plate degradation and fouling in nuclear steam generators (SGs) can lead to SG tube corrosion and loss of efficiency. Inspection and monitoring of these conditions can be integrated with preventive maintenance programs, thereby advancing station-life management processes. A prototype pulsed eddy current (PEC) probe, targeting inspection issues associated with SG tubes in SS410 tube support plate structures, has been developed using commercial finite element (FE) software. FE modeling was used to identify appropriate driver and pickup coil configurations for optimum sensitivity to changes in gap and offset for Alloy-800 SG tubes passing through 25 mm thick SS410 support plates. Experimental measurements using a probe that was manufactured based on the modeled configuration, were used to confirm the sensitivity of differential PEC signals to changes in relative position of the tube within the tube support plate holes. Models investigated the effect of shift and tilt of tube with respect to hole centers. Near hole centers and for small shifts, modeled signal amplitudes from the differentially connected coil pairs were observed to change linearly with tube shift. This was in agreement with experimentally measured TEC coil response. The work paves the way for development of a system targeting the inspection and evaluation of support plate structures in steam generators.

  16. 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

  17. 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.

  18. 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...

  19. 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...

  20. 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.

  1. 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

  2. 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.

  3. 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)

  4. 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.

  5. 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.

  6. 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

  7. 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)

  8. 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

  9. 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.

  10. 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.

  11. 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)

  12. Inspection Database

    Data.gov (United States)

    U.S. Department of Health & Human Services — FDA is disclosing the final inspection classification for inspections related to currently marketed FDA-regulated products. The disclosure of this information is not...

  13. 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.

  14. 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.

  15. New eddy current testing system in steam generator tubes

    International Nuclear Information System (INIS)

    Nagata, Yasuyuki; Shimone, Junri; Maeda, Kotaro; Harada, Yutaka; Murakami, Ryuji

    2003-01-01

    Eddy Current Testing (ECT) technique is applied to PWR Steam Generator (SG) tubes during refueling outage inspection. Bobbin type probe is generally used for the inspection, but it cannot provide sufficient detectability for very tight cracks. NEL, R/D Tech (Canada) and AECL (Canada) jointly developed new ECT probe. The probe is transmit and receive type array probe. It has axial defect detection mode and circumferential defect detection mode. Its inspection speed is as fast as conventional bobbin probe, and detectability performance is same or better than performance of rotating pancake coil (RPC) probe, which is used for detailed inspection. As a tester of the new probe, we have developed new ECT tester TC7700. It is able to transmit composite wave from the 4 independent oscillators (simultaneous excitation system) compared with the conventional inspection system. As regarding for field inspection system, we have integrated Zetec (USA) probe positioner, probe pusher and R/D Tech TC7700. We are also developing new analysis software. The software has automated data screening function, which can deal with large amount of data compared with conventional bobbin probe. We plan to perform a large-scale field trial using the probe and new system in near future. (author)

  16. System for evaluating weld quality using eddy currents

    Science.gov (United States)

    Todorov, Evgueni I.; Hay, Jacob

    2017-12-12

    Electromagnetic and eddy current techniques for fast automated real-time and near real-time inspection and monitoring systems for high production rate joining processes. An eddy current system, array and method for the fast examination of welds to detect anomalies such as missed seam (MS) and lack of penetration (LOP) the system, array and methods capable of detecting and sizing surface and slightly subsurface flaws at various orientations in connection with at least the first and second weld pass.

  17. 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.

  18. 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

  19. Defects and their inspectability by UT in current heavy section steels for nuclear power plant

    International Nuclear Information System (INIS)

    Onodera, S.; Ohkubo, Y.; Takeya, M.; Wataya, M.

    1983-01-01

    The ultrasonic examination (UT, hereinafter) techniques and their equipment have been improved in search of the defects in steels and structures for nuclear power plant components, while the acceptance standards of the defects became continually more stringent in a ''sword and armour'' race. Consequently, the steel making technique had to respond in minimizing the possible defects in steels with successful results in the past two decades. The conventional UT procedures cover basically the following categories of function. 1) Detection and location of defects. 2) Sizing of defects. 3) Characterization of defects. 4) Structure and residual stress effects in ultrasonic field. With proper considerations to the configuration of the steels under examination, the inspectability of the possible defects is further to be optimized. However, the final evaluation has often to be left to the discretion of a competent NDE engineer, well experienced in UT and knowledgeable in steel making. It is therefore the intention of the present paper to review the states-of-the-art of the defects found in the current heavy section steels for primary and secondary components of nuclear power plant, manufactured by the authors' plant. Typical defects, detectable size of them and inspectability of them are discussed

  20. 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)

  1. 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.

  2. 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.

  3. Application of eddy currents to the inspection of fatigue-corroded railway axles

    International Nuclear Information System (INIS)

    Carboni, Michele

    2012-01-01

    Recent experience with existing railway axles indicates that even when they are operated within the design loads, failure can happen due to the synergetic effect of both corrosion and cyclic loads. This synergy is not yet thoroughly understood, however a need for detecting corrosion-fatigue during service is mandatory. In the present paper, corrosion-fatigue tests are carried out, in the lab, on small-scale specimens in order to investigate the possibility to apply eddy currents non-destructive inspection to the detection of corrosion pits and corrosion-fatigue cracks during the service of railway axles. The obtained results are also supported by suitable numerical simulations carried out by a dedicated software package. Part of the presented results were obtained in the frame of the international research project RSSB T728 (just concluded) and the European research project WOLAXIM (still in progress).

  4. 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

  5. Remote field eddy current testing for steam generator inspection of fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Noriyasu, E-mail: noriyasu.kobayashi@toshiba.co.jp [Power and Industrial Systems Research and Development Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan); Ueno, Souichi; Nagai, Satoshi; Ochiai, Makoto [Power and Industrial Systems Research and Development Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan); Jimbo, Noboru [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan)

    2011-12-15

    Highlights: Black-Right-Pointing-Pointer We confirmed defect detection performances of remote field eddy current testing. Black-Right-Pointing-Pointer It is difficult to inspect outer surface of double wall tube steam generator. Black-Right-Pointing-Pointer We used coils with flux guide made of iron-nickel alloy for high sensitivity. Black-Right-Pointing-Pointer Output voltage of detector coil increased more than 100 times. Black-Right-Pointing-Pointer We were able to detect small hole defect of 1mm in diameter on outer surface. - Abstract: We confirmed the defect detection performances of the remote field eddy current testing (RFECT) in order to inspect the helical-coil-type double wall tube steam generator (DWTSG) with the wire mesh layer for the new small fast reactor 4S (Super-Safe, Small and Simple). As the high sensitivity techniques, we tried to increase the direct magnetic field intensity in the vicinity of the inner wall of the tube and decrease the direct magnetic field around the central axis of the tube using the exciter coil with the flux guide made of the iron-nickel alloy. We adopted the horizontal type multiple detector coils with the flux guides arrayed circumferentially to enhance the sensitivity of the radial component. According to the experimental results, the output voltage of the detector coil in the region of indirect magnetic field increased more than 100 times by the application of the exciter and detector coils with the flux guides. Finally, we were able to detect the small hole defect of 1 mm in diameter and 20% of the outer tube thickness in depth over the wire mesh layer by the adoption of the exciter coil and horizontal type multiple detector coils with the flux guides. We also confirmed that the RFECT probe is useful for detecting thinning defects. These experimental results indicated that there is the possibility that we can inspect the double wall tube with the wire mesh layer using the RFECT.

  6. Evaluation of machine learning tools for inspection of steam generator tube structures using pulsed eddy current

    Science.gov (United States)

    Buck, J. A.; Underhill, P. R.; Morelli, J.; Krause, T. W.

    2017-02-01

    Degradation of nuclear steam generator (SG) tubes and support structures can result in a loss of reactor efficiency. Regular in-service inspection, by conventional eddy current testing (ECT), permits detection of cracks, measurement of wall loss, and identification of other SG tube degradation modes. However, ECT is challenged by overlapping degradation modes such as might occur for SG tube fretting accompanied by tube off-set within a corroding ferromagnetic support structure. Pulsed eddy current (PEC) is an emerging technology examined here for inspection of Alloy-800 SG tubes and associated carbon steel drilled support structures. Support structure hole size was varied to simulate uniform corrosion, while SG tube was off-set relative to hole axis. PEC measurements were performed using a single driver with an 8 pick-up coil configuration in the presence of flat-bottom rectangular frets as an overlapping degradation mode. A modified principal component analysis (MPCA) was performed on the time-voltage data in order to reduce data dimensionality. The MPCA scores were then used to train a support vector machine (SVM) that simultaneously targeted four independent parameters associated with; support structure hole size, tube off-centering in two dimensions and fret depth. The support vector machine was trained, tested, and validated on experimental data. Results were compared with a previously developed artificial neural network (ANN) trained on the same data. Estimates of tube position showed comparable results between the two machine learning tools. However, the ANN produced better estimates of hole inner diameter and fret depth. The better results from ANN analysis was attributed to challenges associated with the SVM when non-constant variance is present in the data.

  7. 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.)

  8. 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.

  9. 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

  10. 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)

  11. 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.)

  12. 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

  13. 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)

  14. Development of Inspection Robots for Bridge Cables

    Directory of Open Access Journals (Sweden)

    Hae-Bum Yun

    2013-01-01

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

  15. Development of inspection robots for bridge cables.

    Science.gov (United States)

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

    2013-01-01

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

  16. 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

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

    Science.gov (United States)

    Okafor, A. C.; Natarajan, S.

    2007-03-01

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

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

    International Nuclear Information System (INIS)

    Okafor, A. C.; Natarajan, S.

    2007-01-01

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

  19. 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.

  20. 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)

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. 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.

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

    International Nuclear Information System (INIS)

    Reimann, K.J.

    1980-12-01

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

  7. 49 CFR Appendix C to Part 180 - Eddy Current Examination With Visual Inspection for DOT 3AL Cylinders Manufactured of Aluminum...

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Eddy Current Examination With Visual Inspection... PACKAGINGS Pt. 180, App. C Appendix C to Part 180—Eddy Current Examination With Visual Inspection for DOT 3AL... procedure applicable to the test equipment it uses to perform eddy current examinations. 2. Visual...

  8. 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)

  9. 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

  10. 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.

  11. 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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. Inspection planning

    International Nuclear Information System (INIS)

    Korosec, D.; Levstek, M.F.

    2001-01-01

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

  18. 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

  19. 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)

  20. 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).

  1. 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

  2. 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)

  3. 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)

  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. Development of an eddy current inspection technique for sleeved engine disk bolt holes

    International Nuclear Information System (INIS)

    Palanisamy, R.; Lakin, K.M.

    1983-01-01

    Recent research programs have concentrated mainly on developing techniques to characterize surface breaking cracks and very little has been done towards characterizing subsurface flaws in conducting materials. Presented in this paper are the results of some initial theoretical work aimed at the development of a reliable eddy current technique to detect and characterize defects in engine disk bolt holes under a 0.05'' stainless steel sleeve. The change in impedance of an absolute eddy current coil with and without ferrite core, and the distribution of eddy currents around a second layer crack with and without a thin insulating film between the two conducting layers have been predicted numerically. The overall system development goals and methods to accomplish them are outlined briefly

  6. 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...

  7. 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.

  8. 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

  9. Eddy-current inspection of ferromagnetic tubing using pulsed magnetic saturation

    Energy Technology Data Exchange (ETDEWEB)

    Dodd, C V; Deeds, W E

    1986-07-01

    A pulsed eddy-current system has been designed and developed for nondestructive evaluation of 2.25Cr-1Mo steam generator tubing from the bore side. Since the tubing is ferromagnetic, a large current pulse is sent through a driver coil to produce magnetic saturation all the way through the tube wall. A pickup coil produces an output pulse that is dependent upon the tube properties as well as the driving pulse. The output pulse heights at selected times are used as data that are computer-correlated with calibration data taken from machined standards. Performance data, circuit diagrams, and computer programs are given for the system, which has been demonstrated to detect small flaws located near the outside of a thick ferromagnetic tube.

  10. 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

  11. 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.

  12. 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

  13. THE IMPACT OF THE ACTIONS OF EDUCATION INSPECTION IN THE CURRENT TEACHER TRAINING

    Directory of Open Access Journals (Sweden)

    Miguel Ángel González Ortiz

    2016-06-01

    Full Text Available This article analyses the impact that a priority action on the assessment process in vocational training has had. It has been carried out by the General Education Inspection of Castilla-La Mancha throughout this school year and it is classified within the overall action and training plan for the teachers who teach this level through the Regional Centre for Teacher Training. For the analysis of this work, we took into account the degree of involvement of the teachers who teach middle and upper-grade vocational training who were enrolled in a specific course organised by the Regional Centre for Teacher Training called Didactic syllabi and assessment processes in Vocational Training. These teachers belonged to schools that offer middle and upper-grade vocational training which were supervised by education inspectors of Castilla-La Mancha.The conclusions obtained in the analysis of this work are a true reflection of the performance of education inspection in vocational training.

  14. 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

  15. Examination of pulsed eddy current for inspection of second layer aircraft wing lap-joint structures using outlier detection methods

    Energy Technology Data Exchange (ETDEWEB)

    Butt, D.M., E-mail: Dennis.Butt@forces.gc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada); Underhill, P.R.; Krause, T.W., E-mail: Thomas.Krause@rmc.ca [Royal Military College of Canada, Dept. of Physics, Kingston, Ontario (Canada)

    2016-09-15

    Ageing aircraft are susceptible to fatigue cracks at bolt hole locations in multi-layer aluminum wing lap-joints due to cyclic loading conditions experienced during typical aircraft operation, Current inspection techniques require removal of fasteners to permit inspection of the second layer from within the bolt hole. Inspection from the top layer without fastener removal is desirable in order to minimize aircraft downtime while reducing the risk of collateral damage. The ability to detect second layer cracks without fastener removal has been demonstrated using a pulsed eddy current (PEC) technique. The technique utilizes a breakdown of the measured signal response into its principal components, each of which is multiplied by a representative factor known as a score. The reduced data set of scores, which represent the measured signal, are examined for outliers using cluster analysis methods in order to detect the presence of defects. However, the cluster analysis methodology is limited by the fact that a number of representative signals, obtained from fasteners where defects are not present, are required in order to perform classification of the data. Alternatively, blind outlier detection can be achieved without having to obtain representative defect-free signals, by using a modified smallest half-volume (MSHV) approach. Results obtained using this approach suggest that self-calibrating blind detection of cyclic fatigue cracks in second layer wing structures in the presence of ferrous fasteners is possible without prior knowledge of the sample under test and without the use of costly calibration standards. (author)

  16. Examination of pulsed eddy current for inspection of second layer aircraft wing lap-joint structures using outlier detection methods

    International Nuclear Information System (INIS)

    Butt, D.M.; Underhill, P.R.; Krause, T.W.

    2016-01-01

    Ageing aircraft are susceptible to fatigue cracks at bolt hole locations in multi-layer aluminum wing lap-joints due to cyclic loading conditions experienced during typical aircraft operation, Current inspection techniques require removal of fasteners to permit inspection of the second layer from within the bolt hole. Inspection from the top layer without fastener removal is desirable in order to minimize aircraft downtime while reducing the risk of collateral damage. The ability to detect second layer cracks without fastener removal has been demonstrated using a pulsed eddy current (PEC) technique. The technique utilizes a breakdown of the measured signal response into its principal components, each of which is multiplied by a representative factor known as a score. The reduced data set of scores, which represent the measured signal, are examined for outliers using cluster analysis methods in order to detect the presence of defects. However, the cluster analysis methodology is limited by the fact that a number of representative signals, obtained from fasteners where defects are not present, are required in order to perform classification of the data. Alternatively, blind outlier detection can be achieved without having to obtain representative defect-free signals, by using a modified smallest half-volume (MSHV) approach. Results obtained using this approach suggest that self-calibrating blind detection of cyclic fatigue cracks in second layer wing structures in the presence of ferrous fasteners is possible without prior knowledge of the sample under test and without the use of costly calibration standards. (author)

  17. Development of a 3D electromagnetic model for eddy current tubing inspection application to steam generator tubing

    Energy Technology Data Exchange (ETDEWEB)

    Maillot, V. [Institut de Radioprotection et de Surete Nucleaire, IRSN, 92 - Fontenay aux Roses (France); Pichenot, G.; Premel, D.; Sollier, T. [CEA Saclay, DRT/DECS, 91 - Gif-sur-Yvette (France)

    2003-10-01

    In nuclear plants, the inspection of heat exchanger tubes is usually carried out by using eddy current nondestructive testing. A numerical model, based on a volume integral approach using the Green's dyadic formalism, has been developed, with support from the French Institute for Radiological Protection and Nuclear Safety, to predict the response of an eddy current bobbin coil to 3D flaws located in the tube's wall. With an aim of integrating this model into the NDE multi techniques platform CIVA, it has been validated with experimental data for 2D and 3D flaws. (authors)

  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. 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

  2. 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

  3. 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

  4. 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.

  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. Eddy currents signal processing for steam generator inspection in PWR nuclear power plants

    International Nuclear Information System (INIS)

    Georgel, B.

    1992-01-01

    Steam generator tubes in nuclear power plants are periodically checked by means of eddy current probes. The output of a probe is composed of three types of signals: known events (rolling zone, support plates, U-bend part), noise (mainly metallurgical noise) and possible flaws. The latter are random transients, both in arrival time and in shape: they have to be detected and then estimated, before to be fed to the high level stages of a diagnostic system. The objective of the study presented is to develop a semi-automatic system, which could manage and process more than 1 M-bytes of data per tube and provide an operator with reliable diagnostics proposals within a few minutes. This can be achieved only by cooperation of several digital signal processing techniques: detection, segmentation, estimation, noise subtraction, adaptive filtering, modelization, pattern recognition. The paper describes some of these items

  10. 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.)

  11. 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)

  12. 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)

  13. 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)

  14. 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

  15. 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.

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. Application of risk-informed in-service inspection approach. Pilot study on low pressure emergency core cooling system of NPP Temelin

    International Nuclear Information System (INIS)

    Horacek, L.; Palyza, J.; Zdarek, J.; Vizina, M.

    2004-01-01

    In-service inspection (ISI) programme of piping systems based on Riskinformed In-service Inspections (RI-ISI) approach represents for the WWER NPP licensee first overall systematic conceptual solution of the problems associated with design and design modifications of ISI programme for piping systems. The approach enables to consider possible savings and comparison of in-service inspection programmes according to more objective criteria including those calculated in PSA, in contrast to present much empiric experience collected by manufacturers, operators and ISI vendors in the past. Service experience has shown limited correlation between the deterministic ISI requirements and actual field failures or degradation mechanisms. Where field failures have been observed in piping, they have generally been due to either material concerns (e.g., Intergranular Stress Corrosion Cracking) or stress/cycling mechanisms not identified in the original design basis documents (e.g., thermal stratification), and therefore would not be selected for inspection under current requirements. Risk-informed in-service inspections represent integrated multidisciplinary approach to the in-service inspection programme fulfilling the enhanced requirements of the Czech Regulatory Body (SUJB) for defence in depth concept applied to weld joints of safety related components, application of qualified NDT methods/techniques and introducing of inspections for cause approach. Inspections for cause take into account analysis of both active and potential degradation mechanisms specific to piping system concerned. Simultaneously, this approach enables the licensee to reach, in cases justified from safety point of view, economic savings resulting from lowering of both number and extent of performed in-service inspections and optimisation of their performance. RI ISI pilot study based in majority on EPRI methodology implemented for WWER type reactors has been performed for LP ECCS (Low Pressure Emergency

  1. 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.

  2. 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

  3. 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.

  4. Information-Driven Inspections

    International Nuclear Information System (INIS)

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

    2010-01-01

    determine optimal thresholds; (2) have all separate unattended systems send individual go/no-go signals, allowing the inspectorate to know exactly which systems are exceeding their thresholds; and (3) develop a data aggregation system with attribute monitoring algorithms that would send a single go/no-go or other status signal off-site. Since the data in all of these options are used to inform on-site inspections (which will revert to randomized inspections if no thresholds are reached), the thresholds for the unattended systems can be set much closer to declared operating parameters than in current unattended monitoring systems.

  5. 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

  6. 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.

  7. 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)

  8. 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

  9. 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.

  10. Measurement technology of RF interference current in high current system

    Science.gov (United States)

    Zhao, Zhihua; Li, Jianxuan; Zhang, Xiangming; Zhang, Lei

    2018-06-01

    Current probe is a detection method commonly used in electromagnetic compatibility. With the development of power electronics technology, the power level of power conversion devices is constantly increasing, and the power current of the electric energy conversion device in the electromagnetic launch system can reach 10kA. Current probe conventionally used in EMC (electromagnetic compatibility) detection cannot meet the test requirements on high current system due to the magnetic saturation problem. The conventional high current sensor is also not suitable for the RF (Radio Frequency) interference current measurement in high current power device due to the high noise level in the output of active amplifier. In this paper, a passive flexible current probe based on Rogowski coil and matching resistance is proposed that can withstand high current and has low noise level, to solve the measurement problems of interference current in high current power converter. And both differential mode and common mode current detection can be easily carried out with the proposed probe because of the probe's flexible structure.

  11. 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

  12. 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.

  13. 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

  14. 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

  15. 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.

  16. 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.

  17. 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.)

  18. 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.)

  19. Towards formalization of inspection using petrinets

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  20. Auxiliary Sensor-Based Borehole Transient Electromagnetic System for the Nondestructive Inspection of Multipipe Strings

    Directory of Open Access Journals (Sweden)

    Bo Dang

    2017-08-01

    Full Text Available Transient electromagnetic (TEM techniques are widely used in the field of geophysical prospecting. In borehole detection, the nondestructive inspection (NDI of a metal pipe can be performed efficiently using the properties of eddy currents. However, with increasing concern for safety in oil and gas production, more than one string of pipe is used to protect wellbores, which complicates data interpretation. In this paper, an auxiliary sensor-based borehole TEM system for the NDI of multipipe strings is presented. On the basis of the characteristics of the borehole TEM model, we investigate the principle behind the NDI of multipipe strings using multiple time slices of induced electromotive force (EMF in a single sensor. The results show that the detection performance of NDI is strongly influenced by eddy-current diffusion in the longitudinal direction. To solve this problem, we used time slices of the induced EMF in both the main and auxiliary sensors. The performance of the proposed system was verified by applying it to an oil well with a production casing and liner. Moreover, field experiments were conducted, and the results demonstrate the effectiveness of the proposed method.

  1. 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)

  2. 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.

  3. 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.

  4. 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.

  5. 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)

  6. 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

  7. MODULAR RESEARCH EQUIPMENT FOR ON-LINE INSPECTION IN ADVANCED MANUFACTURING SYSTEMS

    Directory of Open Access Journals (Sweden)

    Davrajh, S.

    2012-11-01

    Full Text Available The significance of inspection processes increases when producing parts with high levels of customer input. These processes must adapt to variations in significant product characteristics. Mass customisation and reconfigurable manufacturing are currently being researched as ways to respond to high levels of customer input. This paper presents the research and development of modular inspection equipment that was designed to meet the on-line quality requirements of mass customisation and reconfigurable manufacturing environments. Simulated results were analysed for application in an industrial environment. The implementation of the equipment in South Africa is briefly discussed. The research indicates that manufacturers need only invest in the required equipment configurations when they are needed for on-line inspection.

  8. 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

  9. 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.

  10. 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).

  11. 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)

  12. Characterizing volumetric discontinuities present in NPP heat exchangers with EASY: an eddy current data analysis system

    International Nuclear Information System (INIS)

    Alencar, Donizete A.; Silva Junior, Silverio F.

    2011-01-01

    Eddy current is a very important NDT inspection method widely used to perform integrity evaluation of tubes installed in heat exchangers. For nuclear power plants, a classical example is the remote inspection of steam generators and condensers, as well as other ordinary auxiliary equipment. Data evaluation can be performed by means of precise phase and amplitude measurements of complex impedance signals, represented as Lissajous figures plotted on the screen of the inspection systems. This paper presents the software EASY, a computer assisted analysis system developed at CDTN to help the characterization of volumetric discontinuities present in heat exchangers tubes. Data to be analyzed are obtained from commercial eddy current equipment data file, such as ECT MAD8D. Main advantage of that system is its portability and easy use, since it can be executed in ordinary PC, under Microsoft Windows operating system. (author)

  13. Characterizing volumetric discontinuities present in NPP heat exchangers with EASY: an eddy current data analysis system

    Energy Technology Data Exchange (ETDEWEB)

    Alencar, Donizete A.; Silva Junior, Silverio F., E-mail: daa@cdtn.b, E-mail: silvasf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    Eddy current is a very important NDT inspection method widely used to perform integrity evaluation of tubes installed in heat exchangers. For nuclear power plants, a classical example is the remote inspection of steam generators and condensers, as well as other ordinary auxiliary equipment. Data evaluation can be performed by means of precise phase and amplitude measurements of complex impedance signals, represented as Lissajous figures plotted on the screen of the inspection systems. This paper presents the software EASY, a computer assisted analysis system developed at CDTN to help the characterization of volumetric discontinuities present in heat exchangers tubes. Data to be analyzed are obtained from commercial eddy current equipment data file, such as ECT MAD8D. Main advantage of that system is its portability and easy use, since it can be executed in ordinary PC, under Microsoft Windows operating system. (author)

  14. Current status of technology development on remote monitoring system

    International Nuclear Information System (INIS)

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

    1997-03-01

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

  15. Qualification of the LF-eddy current technique for the inspection of stainless steel cladding and applications on the reactor pressure vessel

    International Nuclear Information System (INIS)

    Weiss, R.; Becker, R.; Lucht, B.; Mohr, F.; Hartwig, K.

    2001-01-01

    As part of the re-inspection of the reactor pressure vessel of the nuclear power plant, the low-frequency-eddy current technique was implemented during the 1995 outage. Since then, this inspection technique and the testing equipment have seen steady further development. Therefore, optimization of the entire testing system, including qualification based on the 1995 results, was conducted. The eddy current testing system was designed as a ten-channel test system with sensors having separate transmitter and receiver coils. The first qualification of the testing technique and sensors was performed using a single-channel system; a second qualification was then carried out using the new testing electronics. The sensor design allows for a simultaneous detection of surface and subsurface flaws. This assumes that testing is performed simultaneously using four frequencies. Data analysis and evaluation are performed using a digital multi-frequency regression analysis technique The detection limits determined using this technique led to the definition of the following recording limits for testing in which the required signal-to-noise ratio of 6 dB was reliably observed. - Detection of surface connected longitudinal and transverse flaws: - notch, 3 mm deep and 10 mm long, for weave bead cladding; - notch, 2 mm deep and 20 mm long, for strip weld cladding. - Detection of embedded planar longitudinal and transverse flaws: - ligament of 7 mm for 8 mm clad thickness and 3 mm; - ligament for 4 mm clad thickness, notch starting at the carbon steel base material with a length of 20 mm. - Detection of embedded volumetric longitudinal and transverse flaws: - 3 mm diameter side-drilled hole (SDH) for 8 mm clad thickness; ligament, 4 mm. For 4 mm clad thickness: diameter, 2 mm SDH; ligament, 2 mm. All SDHs are 55 mm deep

  16. Contributions of vehicle inspection operations to traffic system in ...

    African Journals Online (AJOL)

    Ethiopian Journal of Environmental Studies and Management. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 10, No 4 (2017) >. Log in or Register to get access to full text downloads.

  17. 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.

  18. Eddy current inspection of tubing; Inspeccion de tubos por corrientes de Foucault

    Energy Technology Data Exchange (ETDEWEB)

    Bauza, J L. R.; Herrero, J; Diaz, J

    1966-07-01

    The Experimental research work carried out to develop a Eddy current testing equipment is described. Search coils with ferrite or air cores were used and the obtained results are discussed. Valuable information was gained from a improved channel in which a direct measure of the defect and the reference signal phase difference is obtained. Artificial defect used to evaluate resolution and sensitivity were produced by electro-machining and mechanical means. Finned SAP tubing was tested in a routine basis with the described equipment and the results plotted. Basic and theoretical considerations on the Eddy current testing technique are given in the last section of this report. (Author)

  19. Plant inspection and maintenance technology

    International Nuclear Information System (INIS)

    Miyahara, Masatoshi; Kanazawa, Masafumi

    1995-01-01

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

  20. Probes for inspections of heat exchanges installed at nuclear power plants type PWR by eddy current method

    International Nuclear Information System (INIS)

    Silva, Alonso F.O.

    2007-01-01

    From all non destructive examination methods usable to perform integrity evaluation of critical equipment installed at nuclear power plants (NPP), eddy current test (ET) may be considered the most important one, when examining heat exchangers. For its application, special probes and reference calibration standards are employed. In pressurized water reactor (PWR) NPPs, a particularly critical equipment is the steam generator (SG), a huge heat exchanger that contains thousands of U-bend thin wall tubes. Due to its severe working conditions (pressure and temperature), that component is periodically examined by means of ET. In this paper a revision of the operating fundamentals of the main ET probes, used to perform SG inspections is presented. (author)

  1. 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)

  2. 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.

  3. 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

  4. 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.

  5. 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

  6. 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)

  7. Implementing hospital quality assurance policies in Iran: balancing licensing, annual evaluation, inspections and quality management systems.

    Science.gov (United States)

    Aghaei Hashjin, Asgar; Delgoshaei, Bahram; Kringos, Dionne S; Tabibi, Seyed Jamaladin; Manouchehri, Jila; Klazinga, Niek S

    2015-01-01

    The purpose of this paper is to provide an overview of applied hospital quality assurance (QA) policies in Iran. A mixed method (quantitative data and qualitative document analysis) study was carried out between 1996 and 2010. The QA policy cycle forms a tight monitoring system to assure hospital quality by combining mandatory and voluntary methods in Iran. The licensing, annual evaluation and grading, and regulatory inspections statutorily implemented by the government as a national package to assure and improve hospital care quality, while implementing quality management systems (QMS) was voluntary for hospitals. The government's strong QA policy legislation role and support has been an important factor for successful QA implementation in Iran, though it may affected QA assessment independency and validity. Increased hospital evaluation independency and repositioning, updating standards, professional involvement and effectiveness studies could increase QA policy impact and maturity. The study highlights the current QA policy implementation cycle in Iranian hospitals. It provides a basis for further quality strategy development in Iranian hospitals and elsewhere. It also raises attention about finding the optimal balance between different QA policies, which is topical for many countries. This paper describes experiences when implementing a unique approach, combining mandatory and voluntary QA policies simultaneously in a developing country, which has invested considerably over time to improve hospital quality. The experiences with a mixed obligatory/voluntary approach and comprehensive policies in Iran may contain lessons for policy makers in developing and developed countries.

  8. 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

  9. 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

  10. 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

  11. 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)

  12. 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.

  13. 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...

  14. 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...

  15. 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.

  16. 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''

  17. Research on Defects Inspection of Solder Balls Based on Eddy Current Pulsed Thermography

    Directory of Open Access Journals (Sweden)

    Xiuyun Zhou

    2015-10-01

    Full Text Available In order to solve tiny defect detection for solder balls in high-density flip-chip, this paper proposed feasibility study on the effect of detectability as well as classification based on eddy current pulsed thermography (ECPT. Specifically, numerical analysis of 3D finite element inductive heat model is generated to investigate disturbance on the temperature field for different kind of defects such as cracks, voids, etc. The temperature variation between defective and non-defective solder balls is monitored for defects identification and classification. Finally, experimental study is carried on the diameter 1mm tiny solder balls by using ECPT and verify the efficacy of the technique.

  18. 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.

  19. 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

  20. Human factors inspection of current control room panel in Jose Cabrera NPP

    International Nuclear Information System (INIS)

    Almeida, P.; O'Hara, J.; Higgins, J.

    2002-01-01

    Within the process of renewal of Exploitation Permit of Jose Cabrera Nuclear Power Plant, UNION FENOSA GENERACIO, S. A. (UFG) has carried out an analysis and evaluation project regarding human factors implications of current control room panel arrangement. The project has been developed in two phases. In the first phase, leaded by EPRI and carried out by experts from SAIC, an independent review from a double viewpoint of human reliability and human factors was developed. In the second phase, a multidisciplinary team (composed by human factors, risk analysis, operation, engineering, training and instrumentation and controls experts) has developed a study on human factors implications of current panel arrangement, following the methodology pointed out in NUREG-0711. The project has been developed under the direction of Brookhaven National Laboratory (BNL), organisation that has authored the aforementioned methodology, with the participation of UFG and SOLUZIONA Ingenieria. For the development of the second study the following steps were taken: Firstly, the potential effects of panel arrangement on crew performance were identified its real evidence was analysed and the goals for the improvement of control room operation were established; following NUREG-0711. After this, several design alternatives that addressed these goals were identified and were analysed along three dimensions: human factors, risk analysis and economic costs. Finally the results of these evaluations were combined using a multi-attribute decision method to arrive at a recommended alternative as he best proposal to incorporate human factors criteria and good practices in the design of control room panels. (Author)

  1. Wavelets transforms and fuzzy logic in the eddy-current inspection of nuclear power plants steam generator tubes

    International Nuclear Information System (INIS)

    Lopez, Luiz Antonio Negro Martin

    2002-01-01

    Nuclear power plants steam generators around the world have presented early damage history in their tubes, caused either by design errors or by inappropriate operation, which besides reducing the availability and the safety of the nuclear power plants it also generates heavy economical burden. To monitor the steam generators operational condition, the Eddy Current testing of their tubes is the non destructive method used to detect, localize, classify and to size the defects. The inspection is performed by inserting probes with coils in the tubes generating a signal correlated to the defect. These signals produced by the probe electric circuit are composed by the resistance and the inductive components which can be combined to produce a Lissajous figure in the complex plane. However, Eddy-Current signals contain noise which induce subjectivity inducing to errors in the inspector diagnosis. It is not uncommon to have different diagnosis from two inspectors about the same signal. The present work has the objective of supplying a methodology to analyze the signals which could help the inspector in the difficult task of interpreting the Eddy Current signals. It is proposed a method to remove the noise based on Wavelets Transforms. It is also proposed a normalization in the signal phase angle measurements. Furthermore, two additional characteristics are also studied, namely: the signal amplitudes and the widths of the Lissajous petals. The use of a Fuzzy Logic based inference engine is also developed and its use is demonstrated to be viable. The defects studied in this work are those which produces volumetric changes in the material. In order to test the proposed methodology, several artificial defects were produced in tubes using different types of materials like: brass, 316L stainless steel and Inconel 600 to produce a experimental data base. An Eddy-Current inspection equipment, the MIZ-17ET was used. Around 1000 time series signals of defects were acquired through

  2. 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.)

  3. Quantitative estimation of defects from measurement obtained by remote field eddy current inspection

    International Nuclear Information System (INIS)

    Davoust, M.E.; Fleury, G.

    1999-01-01

    Remote field eddy current technique is used for dimensioning grooves that may occurs in ferromagnetic pipes. This paper proposes a method to estimate the depth and the length of corrosion grooves from measurement of a pick-up coil signal phase at different positions close to the defect. Grooves dimensioning needs the knowledge of the physical relation between measurements and defect dimensions. So, finite element calculations are performed to obtain a parametric algebraic function of the physical phenomena. By means of this model and a previously defined general approach, an estimate of groove size may be given. In this approach, algebraic function parameters and groove dimensions are linked through a polynomial function. In order to validate this estimation procedure, a statistical study has been performed. The approach is proved to be suitable for real measurements. (authors)

  4. The Defect Inspection on the Irradiated Fuel Rod by Eddy Current Test

    International Nuclear Information System (INIS)

    Koo, D. S.; Park, Y. K.; Kim, E. K.

    1996-01-01

    The eddy current test(ECT) probe of differential encircling coil type was designed and fabricated, and the optimum condition of ECT was derived for the examination of the irradiated fuel rod. The correlation between ECT test frequency and phase and amplitude was derived by performing the test of the standard rig that includes inner notches, outer notches and through-holes. The defect of through-hole was predicted by ECT at the G33-N2 fuel rod irradiated in the Kori-1 nuclear power reactor. The metallographic examination on the G33-N2 fuel rod was Performed at the defect location predicted by ECT. The result of metallographic examination for the G33-N2 fuel rod was in good agreement with that of ECT. This proves that the evaluation for integrity of irradiated fuel rod by ECT is reliable

  5. 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)

  6. 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.

  7. Technical regulation of nondestructive inspection

    International Nuclear Information System (INIS)

    1995-01-01

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

  8. 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)

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. Application of automatic inspection system to nondestructive test of heat transfer tubes of primary pressurized water cooler in the high temperature engineering test reactor. Joint research

    International Nuclear Information System (INIS)

    Takeda, Takeshi; Furusawa, Takayuki

    2001-07-01

    Heat transfer tubes of a primary pressurized water cooled (PPWC) in the high temperature engineering test reactor (HTTR) form the reactor pressure boundary of the primary coolant, therefore are important from the viewpoint of safety. To establish inspection techniques for the heat transfer tubes of the PPWC, an automatic inspection system was developed. The system employs a bobbin coil probe, a rotating probe for eddy current testing (ECT) and a rotating probe for ultrasonic testing (UT). Nondestructive test of a half of the heat transfer tubes of the PPWC was carried out by the automatic inspection system during reactor shutdown period of the HTTR (about 55% in the maximum reactor power in this paper). The nondestructive test results showed that the maximum signal-to-noise ratio was 1.8 in ECT. Pattern and phase of Lissajous wave, which were obtained for the heat transfer tube of the PPWC, were different from those obtained for the artificially defected tube. In UT echo amplitude of the PPWC tubes inspected was lower than 20% of distance-amplitude calibration curve. Thus, it was confirmed that there was no defect in depth, which was more than the detecting standard of the probes, on the outer surface of the heat transfer tubes of the PPWC inspected. (author)

  14. 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.

  15. 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.)

  16. Operational inspections

    International Nuclear Information System (INIS)

    Bystersky, M.

    1997-01-01

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

  17. 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

  18. 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.

  19. 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)

  20. 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.

  1. Design of BEPCII bunch current monitor system

    International Nuclear Information System (INIS)

    Zhang Lei; Ma Huizhou; Yue Junhui; Lei Ge; Cao Jianshe; Ma Li

    2008-01-01

    BEPC II is an electron-positron collider designed to run under multi-bunches and high beam current condition. The accelerator consists of an electron ring, a positron ring and a linear injector. In order to achieve the target luminosity and implement the equal bunch charge injection, the Bunch Current Monitor (BCM) system is built on BEPC II. The BCM system consists of three parts: the front-end circuit, the bunch current acquisition system and the bucket selection system. The control software of BCM is based on VxWorks and EPICS. With the help of BCM system, the bunch current in each bucket can be monitored in the Central Control Room. The BEPC II timing system can also use the bunch current database to decide which bucket needs to refill to implement 'top-off' injection. (authors)

  2. Eddy current magnetic bias x-probe qualification and inspection of steam generator Monel 400 tubing in Pickering Nuclear Generating Station

    International Nuclear Information System (INIS)

    Lepine, B.A.; Van Langen, J.; Obrutsky, L.

    2006-01-01

    This paper presents an overview of the x-probe MB 350 eddy current inspection array probe, for detection of open OD axial crack-like flaws in Monel 400 tubes at Pickering Nuclear Generating Station. This report contains a selection of inspection results from the field inspections performed with this probe during the 2003 and 2004 period at Pickering Nuclear Generating Station A and B. During the 2003 in-service eddy current inspection results of Pickering Nuclear Generating Station A (PNGS-A) Unit 2, a 13 mm (0.5 inch) long axial indication was detected by the CTR1 bobbin and CTR2-C4 array probes in Tube R25-C52 of Steam Generator (SG) 11 in the hot leg sludge pile region. An experimental magnetic bias X-probe, specially designed by Zetec for inspection of Monel 400 tubing, was deployed and the indication was characterized as a potential out diameter (OD) axially oriented crack. Post-inspection tube pulling and destructive examination confirmed the presence of an Environmentally Assisted Crack (EAC), approximately 80% deep and 13mm long. Due to the significance of this discovery, Ontario Power Generation (OPG) requested AECL to initiate a program for qualification of the X-probe MB 350 for the detection of OD axial cracks in medium to high magnetic permeability μ r Monel 400 PNGS-A and B steam generator tubing at different locations. The X-probe MB 350 subsequently has been deployed as a primary inspection probe for crack detection for PNGS steam generators. (author)

  3. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-01

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

  5. 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.

  6. Current and Future Flight Operating Systems

    Science.gov (United States)

    Cudmore, Alan

    2007-01-01

    This viewgraph presentation reviews the current real time operating system (RTOS) type in use with current flight systems. A new RTOS model is described, i.e. the process model. Included is a review of the challenges of migrating from the classic RTOS to the Process Model type.

  7. 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...

  8. An Automated Sensing System for Steel Bridge Inspection Using GMR Sensor Array and Magnetic Wheels of Climbing Robot

    Directory of Open Access Journals (Sweden)

    Rui Wang

    2016-01-01

    Full Text Available Corrosion is one of the main causes of deterioration of steel bridges. It may cause metal loss and fatigue cracks in the steel components, which would lead to the collapse of steel bridges. This paper presents an automated sensing system to detect corrosion, crack, and other kinds of defects using a GMR (Giant Magnetoresistance sensor array. Defects will change the relative permeability and electrical conductivity of the material. As a result, magnetic field density generated by ferromagnetic material and the magnetic wheels will be changed. The defects are able to be detected by using GMR sensor array to measure the changes of magnetic flux density. In this study, magnetic wheels are used not only as the adhesion device of the robot, but also as an excitation source to provide the exciting magnetic field for the sensing system. Furthermore, compared to the eddy current method and the MFL (magnetic flux leakage method, this sensing system suppresses the noise from lift-off value fluctuation by measuring the vertical component of induced magnetic field that is perpendicular to the surface of the specimen in the corrosion inspection. Simulations and experimental results validated the feasibility of the system for the automated defect inspection.

  9. 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.

  10. 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.

  11. 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.)

  12. 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.

  13. Visual Inspection of the Flow Distribution Plate Bolts of a Nuclear Steam Generator

    International Nuclear Information System (INIS)

    Jeong, Woo Tae; Kim, Suk Tae; Sohn, Wook; Kang, Duk Won; Kang, Seok Chul

    2007-01-01

    To develop a system for visually inspecting the flow distribution plate (FDP) bolts of a nuclear steam generator, we reviewed several types of similar inspection equipment. The equipment which are currently available are mostly for inspecting lower part of a steam generator such as tube sheets and annulus except ELVS (Eggcrate Visual Inspection System). However, the design concept of ELVS could not be used for developing a device which enables the visual inspection of flow distribution plate bolts. Therefore, based on the current state of the art technology on the similar equipment, we conceptually designed a new inspection system for checking the FDP bolts

  14. 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.

  15. 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.

  16. 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.

  17. 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

  18. 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.

  19. 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

  20. 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)

  1. 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.

  2. 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.

  3. 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)

  4. 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...

  5. Eddy-current guidance of the automatic inspection machine for the main vessel of the superphenix reactor

    International Nuclear Information System (INIS)

    David, B.; Pigeon, M.

    1985-01-01

    The weld detector device is an eddy-current measurement system consisting of four dual sensors (absolute + differential types), and a control cabinet with eight analog channels. The system delivers all the signals required for computing the correct track of the MIR machine along the welds, irrespective of bend, temperature, width and type of the seam, junctions of seams

  6. 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

  7. 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.)

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. Performance inspection of smart superconducting fault current controller in radial distribution substation through PSCAD/EMTDC simulation

    Energy Technology Data Exchange (ETDEWEB)

    MassoudiFarid, Mehrdad; Shin, Jae Woong; Lee, Ji Ho; Ko, Tae Kuk [Yonsei University, Seoul (Korea, Republic of)

    2013-12-15

    In power grid, in order to level out the generation with demand, up-gradation of the system is occasionally required. This will lead to more fault current levels. However, upgrading all the protection instruments of the system is both costly and extravagant. This issue could be dominated by using Smart Fault Current Controller (SFCC). While the impact of Fault current Limiters (FCL) in various locations has been studied in different situations for years, the performance of SFCC has not been investigated extensively. In this research, SFCC which has adopted the characteristics of a full bridge thyristor rectifier with a superconducting coil is applied to three main locations such as load feeder, Bus-tie position and main feeder location and its behavior is investigated through simulation in presence and absence of small Distributed Generation unit (DG). The results show a huge difference in limiting the fault current when using SFCC.

  1. Sustained currents in coupled diffusive systems

    International Nuclear Information System (INIS)

    Larralde, Hernán; Sanders, David P

    2014-01-01

    Coupling two diffusive systems may give rise to a nonequilibrium stationary state (NESS) with a non-trivial persistent, circulating current. We study a simple example that is exactly soluble, consisting of random walkers with different biases towards a reflecting boundary, modelling, for example, Brownian particles with different charge states in an electric field. We obtain analytical expressions for the concentrations and currents in the NESS for this model, and exhibit the main features of the system by numerical simulation. (paper)

  2. 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

  3. 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)

  4. Eddy Current Thermography: System Development and Its Application in NDT

    International Nuclear Information System (INIS)

    Nurliyana Shamimie Rusli; Ilham Mukriz Zainal Abidin; Sidek, H.A.A.

    2015-01-01

    Eddy Current Thermography (ECT) is an integrative technique which combines eddy current and thermographic NDT in order to provide an efficient method for defect detection. The technique is applicable to electrically conductive material and has the ability to detect surface and subsurface defect. ECT is a non-contact technique; has the ability to provide instantaneous response and high scanning speed that makes it reliable for defect detection and assessment. The technique combines electromagnetic excitation of the work-piece via a coil carrying current, heating of the material by induction and inspection by transient infrared thermography. In this paper, the development of ECT system is detailed, including coil design for global and local heating of samples, and optimisation of excitation parameters (frequency, power, heating duration etc). Results from 3D FEM simulation and experimental investigations are also presented to provide the overview of underlying phenomena and application of ECT. The work demonstrates the effectiveness of the developed ECT system and technique in defect detection and assessment. (author)

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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)

  11. 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

  12. 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)

  13. 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.

  14. Automatic system for ionization chamber current measurements

    International Nuclear Information System (INIS)

    Brancaccio, Franco; Dias, Mauro S.; Koskinas, Marina F.

    2004-01-01

    The present work describes an automatic system developed for current integration measurements at the Laboratorio de Metrologia Nuclear of Instituto de Pesquisas Energeticas e Nucleares. This system includes software (graphic user interface and control) and a module connected to a microcomputer, by means of a commercial data acquisition card. Measurements were performed in order to check the performance and for validating the proposed design

  15. 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)

  16. 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

  17. 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.

  18. 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.

  19. 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.

  20. Development of a uniform eddy current multi-probe for flaw inspection on a curved surface shape portion and estimation of crack shape

    International Nuclear Information System (INIS)

    Fukuoka, Katsuhiro; Hashimoto, Mitsuo

    2009-01-01

    The establishment of non-destructive inspection technology for plant structures is necessary, since the occurrence of cracks has been reported in some nuclear power plants. In this research, a uniform eddy current multi-probe to inspect cracks on a curved structure was developed. We designed exciting coils of this probe, considering the shape of the curved structure, so that the eddy current flows uniformly. Pick-up coils were arranged on a flexible printed circuit board to fit on the curved surface shape portion. The detection characteristics for EDM (electrical discharge machining) slits provided on the curved surface shape portion of the specimen were evaluated. The clear signals for the EDM slits provided on the curved surface which had a curvature radius of 25 mm were obtained by this probe. We confirmed that the crack shape could be estimated by detecting the signals from the developed probe. (author)

  1. 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.

  2. 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

  3. 78 FR 52127 - Tobacco Inspection and Grading Services: Notice of Request for an Extension of a Currently...

    Science.gov (United States)

    2013-08-22

    ... DEPARTMENT OF AGRICULTURE Agricultural Marketing Service [AMS-CN-13-0046] Tobacco Inspection and...: Agricultural Marketing Service, USDA. ACTION: Notice and request for comments. SUMMARY: In accordance with the... 16, 2013. Rex A. Barnes, Associate Administrator, Agricultural Marketing Service. [FR Doc. 2013-20439...

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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.

  9. 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)

  10. 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.

  11. 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)

  12. 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)

  13. 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.

  14. 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

  15. 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

  16. 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)

  17. 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

  18. Direct current power delivery system and method

    Science.gov (United States)

    Zhang, Di; Garces, Luis Jose; Dai, Jian; Lai, Rixin

    2016-09-06

    A power transmission system includes a first unit for carrying out the steps of receiving high voltage direct current (HVDC) power from an HVDC power line, generating an alternating current (AC) component indicative of a status of the first unit, and adding the AC component to the HVDC power line. Further, the power transmission system includes a second unit for carrying out the steps of generating a direct current (DC) voltage to transfer the HVDC power on the HVDC power line, wherein the HVDC power line is coupled between the first unit and the second unit, detecting a presence or an absence of the added AC component in the HVDC power line, and determining the status of the first unit based on the added AC component.

  19. Medical Robots: Current Systems and Research Directions

    Directory of Open Access Journals (Sweden)

    Ryan A. Beasley

    2012-01-01

    Full Text Available First used medically in 1985, robots now make an impact in laparoscopy, neurosurgery, orthopedic surgery, emergency response, and various other medical disciplines. This paper provides a review of medical robot history and surveys the capabilities of current medical robot systems, primarily focusing on commercially available systems while covering a few prominent research projects. By examining robotic systems across time and disciplines, trends are discernible that imply future capabilities of medical robots, for example, increased usage of intraoperative images, improved robot arm design, and haptic feedback to guide the surgeon.

  20. Periodic and in-service inspection programs

    International Nuclear Information System (INIS)

    Dinu, M.

    2000-01-01

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

  1. 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.

  2. 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.

  3. 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.)

  4. 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.

  5. 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.

  6. 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

  7. 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.

  8. Eddy-current testing of nuclear fuel cladding tubes using tilted encircling coil system, 1

    International Nuclear Information System (INIS)

    Yin, Renzhong; Sekine, Kazuyoshi; Shimizu, Hisaji; Tsukui, Kazushige; Urata, Megumu.

    1989-01-01

    The eddy current testing method with external encircling-coils has been widely used as a standard technique for inspection of defects in irradiated zircaloy cladding tubes. In this inspection, the systematic procedure to reliably characterize defects is required. This paper describes the newly developed external tilted encircling-coil system, in which the coil axis is inclined by an angle α to the sample tube axis, for reliable determination of the sort, location and size of defects. As the results of experimental work concerning some kinds of artificial defects in zircaloy cladding tubes using newly designed tilted coil system, an adaptable general-procedure for characterization of defects has been proposed. Furthermore, it has been confirmed that in the case of smaller tilt angles of coil, the signal-to noise ratio for defect response in this coil system is approximately equal to that of ordinary encircling coil system. (author)

  9. Current Hitachi knowledge engineering systems: an overview

    Energy Technology Data Exchange (ETDEWEB)

    Masui, S; Maeda, A; Masuishi, T [Hitachi, Ltd., Tokyo (Japan)

    1992-02-01

    In order to bring the knowledge engineering technology up to the practical phase, Hitachi has provided several knowledge engineering system products, including expert system building tools, knowledge acquisition tools, and many kinds of stand-alone and build-in expert systems in both the business and process control fields. In this review article, an overview of Hitachi{prime}s recent knowledge systems is described, which includes a trend analysis on recent market recognition. In addition, to introduce the Hitachi{prime}s current activities, a new product, a user interface building tool, and a new method of tuning fuzzy membership functions using a neuro-computing algorithm are also described. Furthermore, it is pointed out that not only practical tools and methodologies, but also a practical development team, including a planning section, a cooperating expert, a user section, and experienced knowledge engineers, is needed to achieve practical expert systems. 20 refs., 10 figs., 1 tab.

  10. Analysis and solution of spike current of intermediate range for nuclear instrumentation system

    International Nuclear Information System (INIS)

    Li Xingqiang; Xiao Yu; Xue Bin; Wang Yinli

    2015-01-01

    During the initial start-up of HYH NPP unit 1, spike currents occurred in intermediate range channel of RPN system and reactor trip was triggered. After analyzing the operation principle of intermediate range channel and site inspection, and doing simulating test, the root cause was fixed on the bug of range switching of intermediate range channel. Then a solution based on parameters optimizing was made and executed on site. (authors)

  11. Review of Current Nuclear Vacuum System Technologies

    International Nuclear Information System (INIS)

    Carroll, M.; McCracken, J.; Shope, T.

    2003-01-01

    Nearly all industrial operations generate unwanted dust, particulate matter, and/or liquid wastes. Waste dust and particulates can be readily tracked to other work locations, and airborne particulates can be spread through ventilation systems to all locations within a building, and even vented outside the building - a serious concern for processes involving hazardous, radioactive, or nuclear materials. Several varieties of vacuum systems have been proposed and/or are commercially available for clean up of both solid and liquid hazardous and nuclear materials. A review of current technologies highlights both the advantages and disadvantages of the various systems, and demonstrates the need for a system designed to address issues specific to hazardous and nuclear material cleanup. A review of previous and current hazardous/nuclear material cleanup technologies is presented. From simple conventional vacuums modified for use in industrial operations, to systems specifically engineered for such purposes, the advantages and disadvantages are examined in light of the following criteria: minimal worker exposure; minimal secondary waste generation;reduced equipment maintenance and consumable parts; simplicity of design, yet fully compatible with all waste types; and ease of use. The work effort reviews past, existing and proposed technologies in light of such considerations. Accomplishments of selected systems are presented, including identified areas where technological improvements could be suggested

  12. 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)

  13. Rip current monitoring using GPS buoy system

    Science.gov (United States)

    Song, DongSeob; Kim, InHo; Kang, DongSoo

    2014-05-01

    The occurrence of rip current in the Haeundae beach, which is one of the most famous beaches in South Korea, has been threatening beach-goers security in summer season annually. Many coastal scientists have been investigating rip currents by using field observations and measurements, laboratory measurements and wave tank experiments, and computer and numerical modeling. Rip current velocity is intermittent and may rapidly increase within minutes due to larger incoming wave groups or nearshore circulation instabilities. It is important to understand that changes in rip current velocity occur in response to changes in incoming wave height and period as well as changes in water level. GPS buoys have been used to acquire sea level change data, atmospheric parameters and other oceanic variables in sea for the purposes of vertical datum determination, tide correction, radar altimeter calibration, ocean environment and marine pollution monitoring. Therefore, we adopted GPS buoy system for an experiment which is to investigate rip current velocity; it is sporadic and may quickly upsurge within minutes due to larger arriving wave groups or nearshore flow uncertainties. In this study, for high accurate positioning of buy equipment, a Satellite Based Argumentation System DGPS data logger was deployed to investigate within floating object, and it can be acquired three-dimensional coordinate or geodetic position of buoy with continuous NMEA-0183 protocol during 24 hours. The wave height measured by in-situ hydrometer in a cross-shore array clearly increased before and after occurrence of rip current, and wave period also was lengthened around an event. These results show that wave height and period correlate reasonably well with long-shore current interaction in the Haeundae beach. Additionally, current meter data and GPS buoy data showed that rip current velocities, about 0.2 m/s, may become dangerously strong under specific conditions. Acknowledgement This research was

  14. 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.

  15. 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

  16. 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

  17. 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)

  18. 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

  19. 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

  20. 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.