• Title/Summary/Keyword: Eddy current test

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Development and Calibration of a Plate Type Eddy Current Standard (평판형 와전류 표준 시험편의 개발 및 교정)

  • Kim, Young-Joo;Kim, Young-Gil;Ahn, Bong-Young;Yoon, Dong-Jin
    • Journal of the Korean Society for Nondestructive Testing
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    • v.27 no.5
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    • pp.393-397
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    • 2007
  • Eddy current standard including an artificial slot for the calibration of absolute type surface probe was fabricated. Developed eddy current standard has the electric conductivity and dimensions, and contains artificial slot as established in ASTM E 1629. The width and depth of artificial slot are 0.1 mm and 0.5 mm respectively. This slot was only possible to measure the depth on the two side edges, and impossible for the middle part with general measurement tools. The ultrasonic test method was applied for measuring depth of the middle part of the artificial slot in the standard. Using this method the dimension could be measured successfully with uncertainty about $15\;{\mu}m$. Calibration of eddy current standard for the absolute probe can be performed by this technique.

A Study on Quantitative Flaw Evaluation of Nuclear Power Plant Steam Generator Tube by Ultrasonic Testing (초음파를 이용한 원자력발전소 증기발생기 전열관의 정략적 결함 평가에 관한 연구)

  • Yoon, Byung-Sik;Kim, Yong-Sik;Lee, Hee-Jong;Lee, Yong-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.1
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    • pp.12-17
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    • 2006
  • A steam generator of nuclear power plant has thousands of thin tubes. These tubes play an important role in maintaining the pressure boundary between the primary and secondary side of nuclear power plant. The steam generator tube is easy to be damaged because of the severe operating conditions such as the high temperature and pressure. Therefore, tremendous efforts are made to assess the structural integrity of the steam generator tubes. The eddy current test is the most popular non-destructive test to assess the integrity of the tubes. However, the eddy current test has the limitation to size the flaw accurately because the eddy current signal behavior depends on the total volume of flaw. This paper shows the possibility that the ultrasonic test method can be applied to detect the flaws in the steam generator tubes and to measure them quantitatively. From the test results, it is expected that if the ultrasonic test is put to practical use in the steam generator tube inspection, the inspection results will be improved.

OPGW Corrosion Detection Using Nondestructive Test Method

  • Jeong, Jae-Kee;Yoon, Gi-Gab;Kang, Ji-Won;Yang, Hai-Won
    • Journal of Electrical Engineering and information Science
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    • v.3 no.1
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    • pp.45-50
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    • 1998
  • This paper deals with some characteristics of a nondestructive eddy current detector to measure OPGW(Composite overhead ground wire with optical fiber) corrosion. This detector is designed to automatically run on OPGW and to continuously inspect the corrosion of the line. The impedance of the eddy current coil changing by any corrosion phenomenon of OPGW is analyzed. Several performances of the detector are described and experimental procedures and test results are also given. As a result, it is shown that the implemented detector can be measured some quantitative data for crack, broken wires or severe deteriorations in OPGW. This nondestructive test method would be applied to improve the reliability and efficiency of transmission line in service.

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Intercomparisonn of Techniques for Pressure Tube Inspection of Pressurized heavy Water Reactor (가압 중수로형 원자력발전소 압력관 비파괴검사기술의 상호비교)

  • Lee, Hee-Jong;Kim, Yong-Si;Yoon, Byung-Sik;Lee, Young-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.25 no.4
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    • pp.294-303
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    • 2005
  • This paper describes the analysis results of a series f Round-Robin test that was performed to intercompare inspection and diagnosis techniques for characterization of pressure tube f a pressurized heavy water reactor under the Coordinated Research Project(CRP) of IAEA's nuclear Power Programme. For this test, six nations, Korea, Canada, India, Argentina, Rumania, and China that currently have pressurized heavy water reactors under operation involved, and the "KOR-1" pressure tube sample prepared by Korea was used. Two kinds of NDE technique, ultrasonic and eddy current test, were applied for these tests. The "KOR-1" pressure tube sample contains total 12 artificial flaws such as crack-like EDM notches, wear that is similar to the real flaws and can be produced on the pressure tubes during plant operation. Test results showed that seven laboratories from six nations detected all twelve flaws in "KOR-1" specimen by using ultrasonic and eddy current test methods, and ultrasonic test method was more accurate than eddy current test method in flaw detectin and sizing. ID flaws in pressure tube sample were more easily detected and accurately sized than OD flaws.

Numerical Modeling of the Hall Sensor Signal Used in Pulsed Eddy Current Testing and Comparison of Its Characteristics with a Coil Sensor Signal (홀센서를 사용한 펄스와전류탐상 신호의 수치모델링 및 코일센서 신호와의 특성 비교)

  • Shin, Young Kil
    • Journal of the Korean Society for Nondestructive Testing
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    • v.36 no.6
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    • pp.490-495
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    • 2016
  • Pulsed eddy current (PEC) testing signals have typically been obtained from the electromotive force induced in a sensor coil. However, an increasing number of studies have elected to incorporate the Hall plate as a sensor. Thus, accurate numerical modeling of the Hall sensor signal is necessary. In this study, a PEC probe is designed and a numerical modeling program is written so that Hall sensor signals and coil sensor signals can be calculated simultaneously. First, a step current is used as the input current. The predicted Hall sensor signals show similar characteristics to those of the experimental signals reported by other researchers. The characteristics of the two types of signals are then analyzed and compared as the thickness of test object changes. The results show that the Hall sensor signal provides less information for evaluating the thickness of the test object than the coil sensor signal. The response signals from a pulsed input current are also calculated, and it is confirmed that an equivalent reversed signal pattern appeared after the pulse width at both signals.

The Development of Diagnostic Sensor for Inner Deterioration of Covered Electric Wire (피복전선의 내부 열화 검출용 센서 개발)

  • Kim, Ki-Joon
    • Journal of the Korean Institute of Electrical and Electronic Material Engineers
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    • v.27 no.4
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    • pp.244-249
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    • 2014
  • In this research, it have developed a sensor that could diagnose inner deterioration of covered wires. With this sensor it observed results from simulation, and the attribute required for realization. For simulation it have used FLUX, it have considered all of geometric and electromagnetic information from coil and base metal that influences eddy current sensor's property in order to predict the final result. It assumed there is no mutual inductance in the coil with N number of turns, because equivalent current flows in coil that is continuously connected in eddy current sensor. It assumed circular coil loop draws a circle, always have self inductance, and they are connected in series and overlapped according number of turns (N) in coil, and bobbin configuration. Actual sensor was produced with consideration of inductance and number of turns (N). In conclusion, it were able to test the dependency through results from simulation, actual measurement, and modeling of simulation. It is considered that attributes of respective base metal and structure can be predicted by simulating in advance.

Nondestructive evaluation of wall thinning covered with insulation using pulsed eddy current (펄스와전류를 이용한 보온재 비해체식 배관감육 평가기술)

  • Park, Duck-Gun;Babu, M.K.;Lee, Duk-Hyun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.90-95
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    • 2014
  • Local wall thinning is a point of concern in almost all steel structures such as pipe lines covered with a thermal insulator made up of materials with low thermal conductivity(fiberglass or mineral wool); hence, Non Destructive Technique(NDT) methods that are capable of detecting the wall thinning and defects without removing the insulation are necessary. In this study we developed a Pulsed Eddy Current(PEC) system to detect the wall thinning of Ferro magnetic steel pipes covered with fiber glass thermal insulator and shielded with Aluminum plate. The developed system is capable of detecting the wall thickness change through an insulation of thickness 10cm and 0.4mm aluminum shielding. In order to confirm the thickness change due to wall thinning, two different sensors, a hall sensor and coil sensor were used as a detecting element. In both cases, the results show a very good change corresponding to the thickness change of the test specimen. During these experiments a carbon steel tube of diameter 210mm and a length of 620mm, which is covered with insulator of 95mm thickness was used. To simulate the wall thinning, the thickness of the tube is changed for a specified length such as 2.5mm, 5mm and 8 mm from the inner surface of the tube. A 0.4mm thick Aluminum plate was covered on the Test specimen to simulate the shielding of the insulated pipelines. For both hall sensor and coil detection methods Fast Fourier transform(FFT) was calculated using window approach and the results for the test specimen without Aluminum shielding were summarized which shows a clear identification of thickness change in the test specimen by comparing the magnitude spectra. The PEC system can detect the wall thinning under the 95 mm thickness insulation and 0.4 mm Al shielding, and the output signal showed linear relation with tube wall thickness.

A vision algorithm for finding the centers of steam generator tubes using the generalized symmetry transform (일반화 대칭변환을 이용한 원전 증기발생기 전열관 중심인식 비젼 알고리즘)

  • 장태인;곽귀일
    • 제어로봇시스템학회:학술대회논문집
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    • 1997.10a
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    • pp.1367-1370
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    • 1997
  • This paper presents a vision algorithm for finding the centers of steam generator tubes using the generalized symmetry transform, which is used for ECT(Eddy Current Test) of steam generator tubes in nuclear power plants. The geometrical properties of the image representing steam generator tubes shows that they have amost circular or somewhat elliptic appearances and each tube has strong symmetry about its center. So we apply the generalized symmetry transform to finding centers of steam geneator tubes. But applying the generalized symmetry transform itself without any modification gives difficulties in obtaining the exact centers of steam generator tubes. But applying the generalized symmetry transform itself without any modification gives difficulties in obtaining the exact centers of tubes due to the shadow effect generated by the local light installed inside steam generator. Therefore we make the generalized symmetry transform modified, which uses a modified phase weight function in getting the symmetry magnitude in order to overcome the misleading effect by the local light. The experimental results indicate that the proposed vision algorithm efficiently recongnizes centers of steam generator tubes.

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Thermal Analysis using Thermal Equivalent Circuit Analysis and Finite Element Method of In-wheel Motor (In-wheel 전동기의 열 등가회로 해석 및 유한요소해법을 이용한 열해석)

  • Kim, Kyu-Seob;Lee, Byeong-Hwa;Hong, Jung-Pyo;Nam, Hyuk
    • Proceedings of the KIEE Conference
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    • 2011.07a
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    • pp.941-942
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    • 2011
  • A thermal equivalent circuit of IPMSM considering eddy current loss of PM and core loss of rotor is proposed. This thermal equivalent model is represented by the thermal resistances and thermal capacitances. In order to determine the factor of each parameter, a heating test is processed. Additionally, the eddy current loss of PM is calculated by a transient 3D finite element analysis. Finally, this thermal equivalent model is verified by a temperature test in a 25kW 12-pole/18-slot IPMSM with varying load.

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Field Feasibility Study of an Eddy Current Testing System for Steam Generator Tubes of Nuclear Power Plant (원전 증기발생기 와전류검사 시스템 현장적용 연구)

  • Moon, Gyoon-Young;Lee, Tae-Hun;Kim, In-Chul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.11 no.2
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    • pp.13-19
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    • 2015
  • Steam generator is one of the most important component of nuclear power plant, and it's integrity and reliability are to be assured to high level by pre-service inspection and in-service inspection. To improve the reliability of steam generator heat exchanger tubes and to secure the management of nuclear power plant safely, KHNP CRI recently has developed eddy current testing system for steam generator. KHNP CRI have performed a series of experimental verification and field application to confirm the performance of the developed ECT system in accordance with ASME Code requirements. The ECT system consists of a remote data acquisition unit, an ECT signal acquisition and analysis software, a water chamber robot controller and a probe push-puller. In this paper, we will details of the developed ECT system and the software and their experimental performance. And also we will report the field applying performance and the issues for further steps.