• 제목/요약/키워드: Eddy current testing probe

검색결과 73건 처리시간 0.03초

Eddy Current Signal Analysis for Transmit-Receive Pancake Coil on ECT Array Probe

  • Lee, Hyang-Beom
    • 비파괴검사학회지
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    • 제26권1호
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    • pp.25-29
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    • 2006
  • In this paper, the eddy current signals come from a pair oi transmit-receive (T/R) pancake coil on ECT array Probe are analyzed with the variations of the lift-of and of the distance between transmit and receive coils. To obtain the electromagnetic characteristics of the probes, the governing equation describing the eddy current problems is derived from Maxwell's equation and is solved using three-dimensional finite element method. Eddy current signals from T/R coils on ECT array probe have quite different characteristics compared with ones from impedance coil on rotating pancake coil probe. The results in this paper ran be helpful when the field eddy current signals from ECT array probe are evaluated.

Equivalency Assessment for an Eddy Current System Used for Steam Generator Tubing Inspection

  • Cho, Chan-Hee;Lee, Tae-Hun;Yoo, Hyun-Ju;Moon, Gyoon-Young
    • 비파괴검사학회지
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    • 제35권4호
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    • pp.258-267
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    • 2015
  • Eddy current testing is widely used for inspecting steam generator tubing in nuclear power plants (NPPs). The inspection technique for steam generator tubing in NPPs should be qualified in accordance with examination guidelines. When the components of a qualified system such as eddy current tester, probe, and data analysis program, are changed, the equivalency of the modified system to the originally qualified system must be verified. The eddy current tester is the most important part of an eddy current testing system because it excites and transmits alternating currents to the probe, receives coil impedance of the probe and generates signals for anomalies. The Korea Hydro & Nuclear Power Co., Ltd. (KHNP) developed an eddy current testing system with an eddy current tester and data acquisition-analysis program for inspecting the steam generator tubing in NPPs; this system can be used for an array probe and as a bobbin and rotating probes. The equivalency assessment for the currently developed system was carried out, and we describe the results in this paper.

Development of Magnetic Phase Detection Sensor for the Steam Generator Tube in Nuclear Power Plants

  • Son, De-Rac;Joung, Won-Ik;Park, Duck-Gun;Ryu, Kwon-Sang
    • Journal of Magnetics
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    • 제14권2호
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    • pp.97-100
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    • 2009
  • A new eddy current testing probe was developed to separate the eddy current signal distortion caused by permeability variation clusters and ordinary defects created in steam generator tubes. Signal processing circuits were inserted into the probe to increase the signal-to-noise ratio and allow digital signal transmission. The new probe could measure and separate the magnetic phases created in the steam generator tubes in the operating environment of a nuclear power plant. Furthermore, the new eddy current testing probe can measure the defects in steam generator tubes as rapidly as a bobbin probe with enhanced testing speed and reliability of defect detection.

와전류탐상을 위한 PC 프로브의 특성해석 및 설계 (Characteristic Analysis and Design of PC Probe for Eddy Current Testing)

  • 김용택;이향범
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2004년도 하계학술대회 논문집 B
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    • pp.965-967
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    • 2004
  • In this paper, characteristic analysis of PC(Pancake Coil) probe with the size variation is presented for eddy current testing. Characteristics of probe are numerically calculated by using the finite element method. From the numerical analysis, the optimum frequency and groups for an experiment are selected. Probes are made and experiment is performed. From the experimental results, the probe shows maximum sensitivity when the size of defect is equal to the size of probe and when the inside diameter is similar to the width of probe and when the height is low. The result can be helpful to the standard of design of PC probe for eddy current testing.

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원전 증기발생기 세관 검사를 위한 와전류 탐상 프로브의 현황 및 전망 (Present Condition and View of Eddy Current Testing Probe for Nuclear Power Plant Steam Generator Tube Examination)

  • 김지호;이향범
    • 한국정보통신설비학회:학술대회논문집
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    • 한국정보통신설비학회 2006년도 하계학술대회
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    • pp.241-245
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    • 2006
  • In the examination of Steam Generator (SG) tube in Nuclear Power Plant (NPP) Eddy Current Testing (ECT) probes play an Important role in detecting the defects. Bobbin probe and Rotating Pancake Coil (RPC) probe is usually used for the inspection of SG tube. Bobbin probe is good at high speed inspection, but ability of detection of circumferential defect is very weak. On the contrary RPC probe, which moves for inspection in the direction of axial and circumferential simultaneously, has very slow inspection speed, but it was excellent detection capability fur small cracks, which is hardly detected by bobbin probe. Many examinations of SG tube examination of NPP are achieved during short period. Therefore, solution about this must develop probe of new form for examination performance and examination time shortening of other probe. In this paper, analyzed technological present condition of Bob-bin probe and RPC probe been using in Nondestructive Testing (NDT) for SG tube defect detection and Appeared about background theory and view of developed probe newly.

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송수신 모드 배열 코일 와전류 탐촉자의 특성 연구 및 이를 이용한 표면검사 (Study on Characteristics of Eddy Current Array Coil Operated in Transmit-Receive Mode and Surface Inspection Using This Probe)

  • 이태훈;지동현;조찬희;김인철
    • 비파괴검사학회지
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    • 제37권1호
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    • pp.21-28
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    • 2017
  • 배열 와전류 기술은 2차원적으로 나란히 정열된 다수의 와전류 코일로 구성된 탐촉자 면적에 대하여 기계적인 이동없이 전기적으로 주사할 수 있다. 단일 코일을 사용하는 와전류 기술과 비교하여 탐촉자가 한 번의 이동으로 넓은 영역을 검사할 뿐만 아니라 데이터 해석이 용이하여 검사 속도와 신뢰성을 향상시키는 장점이 있다. 이번 연구에서는 $2{\times}16$ 코일 배열의 배열 와전류 탐촉자와 순차적으로 송수신 코일을 선택하고 송수신 모드로 동작시키는 다중화기기를 개발하였다. 이 탐촉자를 이용하여 다양한 종류의 시편을 제작하여 표면검사를 수행하고, 와전류 신호 및 C-scan을 이미지 분석을 통해 송수신 모드 배열 와전류 기술의 특성에 대해 연구하였다.

A Study on 3-Dimensional Profilometry of Steam Generator Tube Using a New Eddy Current Probe

  • Kim, Young-Kyu;Song, Myung-Ho;Choi, Myung-Sik
    • 비파괴검사학회지
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    • 제30권3호
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    • pp.225-235
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    • 2010
  • There are many types of the geometric transitions such as dent, bulge, protrusion, expansion, etc, on the inner and outer surfaces of heat exchanger tubes, steam generator tubes, and condenser tubes of nuclear power plants. Such geometric transition causes a local residual stress in heat exchanger tubes and acts as a structural factor accelerating the evolution of defects, in particular stress corrosion cracks. In the conventional eddy current test methods, the bobbin coil profilometry can provide 2-dimensional geometric information on the variation of the average inner diameter along the tube length, but the 3-dimensional distribution and the quantitative size of a local geometric transition existing in the tube cannot be measured. In this paper, a new eddy current probe, developed for the 3-dimensional profile measurement, is introduced and its superior performance is compared with that from the conventional bobbin coil profilometry for the various types of geometric transition. Also, the accuracy of the probe for the quantitative profile measurement is verified by comparing the results with that from the laser profilometry. It is expected that the new eddy current probe and techniques can be effectively used for an optimization of the tube expansion process, and the management of tubes with geometric transitions in service.

Comparison of ECT Probes in Diagnosis of Defects

  • Mun, Ho-Young;Kim, Chang-Eob
    • Journal of Electrical Engineering and Technology
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    • 제9권1호
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    • pp.190-196
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    • 2014
  • In this paper, the characteristics of a defective elliptical aluminum plate are analyzed by three different eddy current testing probes; T/R, T/T, and Impedance probes. The analysis was done by 3D finite element method, and the impedance change of real and imaginary voltage values were analyzed.

외삽 차동형 탐촉자를 사용한 연구로용 핵연료봉의 와전류탐상 (Eddy Current Testing using Encircling Differential Probe for Research Reactor Fuel Rods)

  • 이윤상;김창규
    • 비파괴검사학회지
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    • 제21권5호
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    • pp.561-564
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    • 2001
  • 연구로인 하나로의 핵연료봉은 제조 시 피복층에 품질 관리 절차에서 규정한 크기 이상의 결함이 없도록 와전류탐상 검사를 하도록 되어 있다. 와전류탐상검사 절차를 수립하기 위하여 외삽 차동형 와전류탐촉자 및 표준시험편을 제작하였다. 임피던스 분석기를 사용하여 제작된 탐촉자에 대한 임피던스값을 측정하여 검사주파수 영역에서 최대감도를 얻도록 제작되었는지를 조사하였고, 이 탐촉자 및 MIZ-40A 와전류탐상기를 사용하여, 요구되는 결함 크기를 검출할 수 있는가를 조사하였다. 그 결과 이 탐촉자를 사용하여 길이 2mm 피복 두께 대비 깊이 10%인 인공 노치를 검출할 수 있었으며, 연구로용 핵연료봉의 제조 시 피복층에 존재하는 결함을 성공적으로 검사할 수 있었다.

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