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    A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002::page 21003
    Author:
    Tamura, Akinori
    ,
    Zhong, Chenghuan
    ,
    Croxford, Anthony J.
    ,
    Wilcox, Paul D.
    DOI: 10.1115/1.4035466
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A pipe-wall thinning measurement is a key inspection to ensure the integrity of the piping system in nuclear power plants. To monitor the integrity of the piping system, a number of ultrasonic thickness measurements are manually performed during the outage of the nuclear power plant. Since most of the pipes are covered with an insulator, removing the insulator is necessary for the ultrasonic thickness measurement. Noncontact ultrasonic sensors enable ultrasonic thickness inspection without removing the insulator. This leads to reduction of the inspection time and reduced radiation exposure of the inspector. The inductively-coupled transducer system (ICTS) is a noncontact ultrasonic sensor system which uses electromagnetic induction between coils to drive an installed transducer. In this study, we investigated the applicability of an innovative ICTS developed at the University of Bristol to nuclear power plant inspection, particularly pipe-wall thinning inspection. The following experiments were performed using ICTS: thickness measurement performance, the effect of the coil separation, the effect of the insulator, the effect of different inspection materials, the radiation tolerance, and the measurement accuracy of wastage defects. These initial experimental results showed that the ICTS has the possibility to enable wall-thinning inspection in nuclear power plants without removing the insulator. Future work will address the issue of measuring wall-thinning in more complex pipework geometries and at elevated temperatures.
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      A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4235309
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    contributor authorTamura, Akinori
    contributor authorZhong, Chenghuan
    contributor authorCroxford, Anthony J.
    contributor authorWilcox, Paul D.
    date accessioned2017-11-25T07:18:40Z
    date available2017-11-25T07:18:40Z
    date copyright2017/1/3
    date issued2017
    identifier issn2332-8983
    identifier otherners_003_02_021003.pdf
    identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235309
    description abstractA pipe-wall thinning measurement is a key inspection to ensure the integrity of the piping system in nuclear power plants. To monitor the integrity of the piping system, a number of ultrasonic thickness measurements are manually performed during the outage of the nuclear power plant. Since most of the pipes are covered with an insulator, removing the insulator is necessary for the ultrasonic thickness measurement. Noncontact ultrasonic sensors enable ultrasonic thickness inspection without removing the insulator. This leads to reduction of the inspection time and reduced radiation exposure of the inspector. The inductively-coupled transducer system (ICTS) is a noncontact ultrasonic sensor system which uses electromagnetic induction between coils to drive an installed transducer. In this study, we investigated the applicability of an innovative ICTS developed at the University of Bristol to nuclear power plant inspection, particularly pipe-wall thinning inspection. The following experiments were performed using ICTS: thickness measurement performance, the effect of the coil separation, the effect of the insulator, the effect of different inspection materials, the radiation tolerance, and the measurement accuracy of wastage defects. These initial experimental results showed that the ICTS has the possibility to enable wall-thinning inspection in nuclear power plants without removing the insulator. Future work will address the issue of measuring wall-thinning in more complex pipework geometries and at elevated temperatures.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleA Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection
    typeJournal Paper
    journal volume3
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4035466
    journal fristpage21003
    journal lastpage021003-9
    treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002
    contenttypeFulltext
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