• Title/Summary/Keyword: Nuclear inspection

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A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I) (원자력발전소(原子力發電所) 가동중(稼動中) 검사(檢査)의 시험분석(試驗分析)을 위한 자동화연구(自動化硏究) (I))

  • Kim, W.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.5 no.1
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    • pp.34-47
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    • 1985
  • The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during preservice and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant ${\ast}$ General Requirement. ${\ast}$ Principle and Methods of Ultrasonic Test. ${\ast}$ Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspite of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huze system, the more notice should be concentrated as follows. Establishing rational operation plan, developing various technology, and making the newly designed system for undeveloped sector.

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A development on the inspection technologies for secondary electrical facilities in nuclear power plant (원전 2차측 전력설비 검사기술 개발)

  • Park, Hyun-Shin;Kim, Kern-Joong;Kim, Moon-Young
    • Proceedings of the KIEE Conference
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    • 2005.11b
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    • pp.110-112
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    • 2005
  • Recently, the reactor trip in nuclear power plants has mostly occurred by the failure of secondary electrical facilities. Some kinds of technical standards or acceptable criteria are required to regulate those facilities. Therefore, in this paper the failures of secondary electrical facilities which cause reactor trip are analyzed, and the inspection technologies including guidelines for secondary electrical facilities are developed.

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Automatic Inspection Technology for Small Bore Penetration Nozzle in High Radiation Area of Nuclear Power Plant (원자력발전 고방사선구역 소구경 노즐에 대한 자동화검사 기술)

  • Ryu, Sung Woo;Yoon, Kee Bong;Jeon, Gyu Min;Seong, Un Hak
    • Journal of the Korean Society for Nondestructive Testing
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    • v.36 no.6
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    • pp.504-509
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    • 2016
  • Defects in dissimilar metal welds are reported to be on the increase during the operating lifespan and aging of nuclear power plants. In Korea, reported cases of defects due to dissimilar metal welds include the drain nozzle of a steam generator and RCS hot tube sampling nozzles. Therefore, there is an urgent need to develop a reliable automated nondestructive inspection technique and a system for the inspection of dissimilar metal welds of small diameter nozzles in a high radiation area of a nuclear power plant. In this study, to ensure effective defect inspection of small diameter nozzles (RCS high-temperature tube sampling nozzle) of a nuclear power plant, three different methods were developed. These include: (1) optimum inspection probe design by beam simulation, (2) multi-directions UT optimum inspection technique for the inspection of small diameters of different welded parts, and (3) remote control automatic inspection system. The developed technique and systems have been verified to be suitable for use in the inspection of defects in smaller diameter nozzles in nuclear power plants.

The Development of Underwater Robotic System and Its application to Visual Inspection of Nuclear Reactor Internals (수중로봇 시스템의 개발과 원자로 압력용기 육안검사에의 적용)

  • 조병학;변승현;신창훈;양장범
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2004.10a
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    • pp.1327-1330
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    • 2004
  • An underwater robotic system has been developed and applied to visual inspection of reactor vessel internals. The Korea Electric Power Robot for Visual Test (KeproVt) consists of an underwater robot, a vision processor-based measuring unit, a master control station and a servo control station. The robot guided by the control station with the measuring unit can be controlled to have any motion at any position in the reactor vessel with $\pm$1 cm positioning and $\pm$2 degrees heading accuracies with enough precision to inspect reactor internals. A simple and fast installation process is emphasized in the developed system. The developed robotic system was successfully deployed at the Younggwang Nuclear Unit 1 for the visual inspection of reactor internals.

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Evaluation of the characteristics of the reflection plate to measure defects in the invisible area using infrared thermography

  • Kim, Sang Chae;Park, Il Cheol;Kang, Chan Geun;Jung, Hyunchul;Chung, Woon Kwan;Kim, Kyeong Suk
    • Nuclear Engineering and Technology
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    • v.52 no.4
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    • pp.856-862
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    • 2020
  • Defect inspection system for industrial applications takes the important portion. Non-destructive inspection method has been significantly improved. Infrared thermography, as one of method for non-destructive inspection, can provide relatively precise data and quick inspection time. This study, it was performed to measure defect according to the measurement limit of the non-visible areas such as the back surface of the pipe using reflection plate using reflection plate based on Infrared thermography. The materials of the reflection plate were determined in consideration of the space limitation and the thermal characteristics, and defects were detected by the manufactured reflection plate. Detection of defect in non-visible area using the candidate materials for reflection plate was conducted.

Development of the Life Management D/B System for Concrete Structures in Nuclear Power Plants (원전 콘크리트 구조물의 수명관리 D/B 시스템 개발)

  • 이종석;김도겸;함영승;임재호;송영철;조명석
    • Proceedings of the Korea Concrete Institute Conference
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    • 1998.10b
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    • pp.637-642
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    • 1998
  • This study was performed to develop effective management system of concrete structures in Nuclear Power Plants. This D/B system includes three kinds of data : 1)visual inspection data(cracking, spalling, etc.) 2) durability data carbonation, chloride attack, etc. 3) in-service inspection data(prestressing force. material properties, etc. ) By using the life management D/B System, the field engineers can easily acquire the information about the various inspection data. repair and accidental histories of structures. This system, will contribute to the efficient life management of concrete structures.

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Pipe Inspection Robot Using an Inch-Worm Mechanism with Embedded Pneumatic Actuators

  • Choi, Chang-Hwan;Jung, Seung-Ho;Kim, Seung-Ho
    • 제어로봇시스템학회:학술대회논문집
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    • 2005.06a
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    • pp.346-351
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    • 2005
  • The outlet feeder pipe thinning in a PHWR (Pressurized Heavy Water Reactor) is caused by high pressure steam flow inside the pipe, which is a well known degradation mechanism called FAC (Flow Assisted Corrosion). In order to monitor the degradation, the thickness of the outlet bends closed to the exit of the pressure tube should be measured and analyzed at every official overhaul. This paper develops a mobile feeder pipe inspection robot that can minimize the irradiation dose of human workers by automating the measurement process. The robot can move by itself on the feeder pipe by using an inch worm mechanism, which is constructed by two gripper bodies that can fix the robot body on the pipe, one extendable and contractable actuator, and a rotation actuator connected the two gripper bodies to move forward and backward, and to rotate in the circumferential direction

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Development of a Web-based Fatigue Life Evaluation System for Primary Components in a Nuclear Power Plant (원자력발전소 1 차 계통 주요기기에 대한 웹기반 피로수명평가 시스템 개발)

  • Seo, Hyong-Won;Lee, Sang-Min;Choi, Jae-Boong;Kim, Young-Jin;Choi, Sung-Nam;Jang, Ki-Sang;Hong, Sung-Yull
    • Proceedings of the KSME Conference
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    • 2003.04a
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    • pp.279-284
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    • 2003
  • A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

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