• 제목/요약/키워드: Vessel inspection

검색결과 154건 처리시간 0.035초

Development of an Integrated Reactor UT Inspection System

  • Park, Yoo-Rark;Lee, Jae-Cheol
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2001년도 ICCAS
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    • pp.133.6-133
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    • 2001
  • Reactor vessel is one of the most important equipment of Nuclear Power Plant (NPP) with regard to the nuclear safety. Thus reactor vessel must be examined periodically by certified experts. Currently, ultra-sonic(UT) non-destructive inspection is executed on reactor vessel. Two different techniques are used in this inspection. One is using the movable manipulator fixed with the support-guide placed on the vessel, and the other is using mobile robot moving in the vessel. Movable manipulator machine is very heavy, hard to handle, and very expensive. Mobile robot equipment is small and convenient but has a weak point on positional precision. To solve these problems we developed a reactor inspection system based on laser-driven mobile robot. This paper describes the main concept and structure of integrated inspection units and the feature of implemented units.

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Automatic Inspection of Reactor Vessel Welds using an Underwater Mobile Robot guided by a Laser Pointer

  • Kim, Jae-Hee;Lee, Jae-Cheol
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2004년도 ICCAS
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    • pp.1116-1120
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    • 2004
  • In the nuclear power plant, there are several cylindrical vessels such as reactor vessel, pressuriser and so on. The vessels are usually constructed by welding large rolled plates, forged sections or nozzle pipes together. In order to assure the integrity of the vessel, these welds should be periodically inspected using sensors such as ultrasonic transducer or visual cameras. This inspection is usually conducted under water to minimize exposure to the radioactively contaminated vessel walls. The inspections have been performed by using a conventional inspection machine with a big structural sturdy column, however, it is so huge and heavy that maintenance and handling of the machine are extremely difficult. It requires much effort to transport the system to the site and also requires continuous use of the utility's polar crane to move the manipulator into the building and then onto the vessel. Setup beside the vessel requires a large volume of work preparation area and several shifts to complete. In order to resolve these problems, we have developed an underwater mobile robot guided by the laser pointer, and performed a series of experiments both in the mockup and in the real reactor vessel. This paper introduces our robotic inspection system and the laser guidance of the mobile robot as well as the results of the functional test.

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원자로 초음파 검사 로봇 주제어 시스템 개발 (Development of A Main Control System for Reactor UT Inspect ion Robot)

  • 최유락;이재철;김재희
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2000년도 제15차 학술회의논문집
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    • pp.288-288
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    • 2000
  • Reactor vessel is one of the most important equipment with regard to the safety of nuclear power plant. Thus nuclear regulation requires its periodical examination by certified inspection experts. Conventional reactor inspection machines are obsolete, hard to handle, and very expensive. To solve these problems we developed robotic reactor vessel inspection system which are small, easy to use for inspection, cost effective, and convenient in operation. This paper describes the main features of Main Control System which is one part of robotic inspection equipment we developed.

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원자로 헤드 관통관 노즐 가동전 검사 수행 (Pre-Service Inspection for Reactor Vessel Penetration Nozzle)

  • 이동진;노익준;신건철;김해석;홍주열;최정권
    • 한국압력기기공학회 논문집
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    • 제6권2호
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    • pp.9-15
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    • 2010
  • US NRC issued rulemaking of 10CFR50.55a to perform the Perservice and Inservice inspection for Reactor Vessel Head Penetration Nozzle of US Nuclaer plant. The rulemaking was required the EPRI Demonstration to verify the NDE technique performing special Ultrasonic examination. In order to meet this requirement, the UT and ECT procedures was demonstrated and the NDE personnel were qualified by EPRI. In this paper, the NDE technique and analysis method are described the Preservice inspection for the Palo Verde #1/2/3 Replacement Reactor Vessel Head Penetration Nozzle using the qualified procedures and personnel.

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Development of gamma ray scanning coupled with computed tomographic technique to inspect a broken pipe structure inside laboratory scale vessel

  • Saengchantr, Dhanaj;Srisatit, Somyot;Chankow, Nares
    • Nuclear Engineering and Technology
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    • 제51권3호
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    • pp.800-806
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    • 2019
  • This paper presents a laboratory experiment on data acquisition technique that applied to the gamma radiation scanning coupled with computed tomography (CT) technique for inspection of broken nozzle inside the vertical vessel. The acquisition technique was developed to inspect a large diameter vessel when suspicious problem location is not easily accessed. This technique allows the installation of gamma radiation source (Cesium 137, Cs-137), and detectors (Sodium Iodine. NaI(Tl)) from the accessible location to the required location and performs the scanning by designed pattern. To demonstrate the designed technique, top opened tank which installed with six cut steel pipes diameter of 76.2 mm (3") at a certain position was selected. They were assumed to be a gas riser pipes inside the vessel. Three studied cases were performed, (a) projection of well installed six pipes, (b) projection of one out of six broken pipe and (c) one of nozzle was assumed to be failure and fell down until one out of six pipes was broken and obstructed by nozzle. Results clearly indicated the capability of developed technique to distinguish between normal situation case and abnormal situation cases.

KSTAR 토카막용 저온용기 개발 (Development of the Cryostat Vessel for KSTAR Tokamak)

  • 허남일;김병철;홍권희;김근홍;신훈;박경호;박주식
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 추계학술대회
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    • pp.545-550
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    • 2004
  • KSTAR cryostat is a 8.8 m diameter vacuum vessel that provides the necessary thermal barrier between the ambient temperature test cell and the supercritical helium cooled superconducting magnet providing the base pressure of 1 ${\times}$ $10^{-3}Pa$. The cryostat is a single walled vessel consisting of central cylindrical section and two end closures, a flat base structure with external reinforcements and a dome-shaped lid structure. The base structure has 8 equally spaced support legs anchored on the concrete base. The cryostat vessel design was executed to satisfy the performance and operation requirements. The major loads considered in the structural analysis were vacuum pressure, dead weight, electromagnetic load driven by plasma disruption, and seismic load. Based on the fabrication and inspection procedures for the vessel, cryostat vessel was fabricated and inspected. It was confirmed that the inspection results were acceptable.

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

  • 조병학;변승현;신창훈;양장범
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2004년도 추계학술대회 논문집
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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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원자로 BMI 노즐 검사를 위한 자동화 비파괴검사 시스템 개발 (Development of Automated Nondestructive Inspection System for BMI Nozzles in Nuclear Vessel)

  • 박준수;이원근;한원진;이선호;성운학
    • 비파괴검사학회지
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    • 제33권1호
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    • pp.26-33
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    • 2013
  • 원자로 BMI 노즐은 원자력발전 설비의 운영을 위한 핵심요소 중 하나이며 하부헤드에 설치되어 있다. 상부헤드에 비해 비교적 저온영역에 있지만 최근 외국사례에 비추어 볼 때 PWSCC의 발생 가능성이 크기 때문에 가동중 비파괴검사가 반드시 필요하다. 그러나 BMI 노즐은 원자로 하부에 있기 때문에 고방사선 구역이며 원자로 내부는 붕산수로 채워져 있기 때문에 접근이 매우 어렵다. 본 연구에서 BMI 노즐 검사를 위하여 TOFD를 이용한 탐촉자를 개발하였고, 자동화검사를 위해 내방수 기능을 가진 스캐너를 개발하였다. 또한, BMI 노즐과 동일한 재질 및 형상으로 인공결함시험편을 제작하여 자동화 비파괴검사 시스템의 성능검증을 수행하였다.