• Title/Summary/Keyword: 비파괴검사학회

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Models of Reliability Assessment of Ultrasonic Nondestructive Inspection (초음파 비파괴검사의 신뢰도 평가 모델)

  • Park, I.K.;Park, U.S.;Kim, H.M.;Park, Y.W.;Kang, S.C.;Choi, Y.H.;Lee, J.H.
    • Journal of the Korean Society for Nondestructive Testing
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    • v.21 no.6
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    • pp.607-611
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    • 2001
  • Ultrasonic inspection system consist of the operator, equipment and procedure. The reliability of results in ultrasonic inspection is affected by its ability. Furthermore, the reliability of nondestructive testing is influenced by the inspection environment, materials and types of defect. Therefore, it is very difficult to estimate the reliability of NDT due to the various factors. In this study, the probability of detection by logistic probability model and Monte Carlo simulation is used for the reliability assessment of ultrasonic inspection. The utility of the NDT reliability assesment is verified by the analysis of the data from round robin test nth these models.

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Simulation of Time of Flight Diffraction Signals for Reactor Vessel Head Penetrations (원자로 상부 헤드 관통관 TOFD 신호 시뮬레이션)

  • Lee, Tae-Hun;Kim, Young-Sik;Lee, Jeong-Seok
    • Journal of the Korean Society for Nondestructive Testing
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    • v.36 no.4
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    • pp.273-280
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    • 2016
  • The simulation of nondestructive testing has been used in the prediction of the signal characteristics of various defects and in the development of the procedures. CIVA, a simulation tool dedicated to nondestructive testing, has good accuracy and speed, and provides a three-dimensional graphical user interface for improved visualization and familiar data displays consistent with an NDE technique. Even though internal validations have been performed by the CIVA software development specialists, an independent validation study is necessary for the assessment of the accuracy of the software prior to practical use. In this study, time of flight diffraction signals of ultrasonic inspection of a calibration block for reactor vessel head penetrations were simulated using CIVA. The results were compared to the experimentally inspected signals. The accuracy of the simulated signals and the possible range for simulation were verified. It was found that, there is a good agreement between the CIVA simulated and experimental results in the A-scan signal, B-scan image, and measurement of depth.

Development of Automated Nondestructive Inspection System for BMI Nozzles in Nuclear Vessel (원자로 BMI 노즐 검사를 위한 자동화 비파괴검사 시스템 개발)

  • Park, Joon Soo;Lee, Won Kun;Han, Won Jin;Lee, Sun Ho;Seong, Un Hak
    • Journal of the Korean Society for Nondestructive Testing
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    • v.33 no.1
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    • pp.26-33
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    • 2013
  • BMI nozzles in bottom head of the nuclear vessel are one of major components in nuclear power plants. The BMI nozzles have high possibility to generate PWSCC(primary water stress corrosion crack) according to recent foreign case although operation temperature is lower then the upper head of the nuclear vessel. Thus, nondestructive inspection of the BMI nozzles is required. But, inspection of BMI nozzles is not easy since the BMI nozzles placed in high radiated area and inside the nozzles filled with boric acid. Thus, in this study, a TOFD transducer for inspection of BMI and automated scanner system with water were developed. Also, validation of performance of the developed transducer and system are performed using specimens with artificial defects.

비파괴 검사기술을 이용한 원자력 발전설비 예방진단

  • 박상기;권오철
    • 전기의세계
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    • v.38 no.11
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    • pp.55-62
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    • 1989
  • 원자력 발전소의 건설 및 운전은 설계, 제작, 건설 및 운전등에 이르기까지 안전에 대한 고려가 치밀하게 이루어지고 있으며 그중에서도 원자력 부품의 제작, 설치시는 물론이고 원전의 건설후 사용전 및 사용중에 수시 또는 정기적으로 거의 모든 중요한 부품들에 대한 비파괴 검사는 필수적이며 제반 법규 및 규격도 원자력발전 설비에 대한 요건을 엄격하게 규정하고 있다. 국내에 운전중인 모든 원전에 대해서도 제반 법규 및 규격요건에 따른 제작/설치 검사와 가동전 및 가동중 검사를 첨단기술을 이용하여 엄격리 실시하여 발견될 주요결함은 수리조차하고 있으며 미세한 결함까지도 기록관리하며 가동중 검사에서 이들의 성장 뿐 아니라 새로운 결함의 생성들을 찾아냄으로써 원전의 안전성 확보와 가동율 향상이라는 소기의 목적을 위해 원전의 예방진단에 만전을 기하고 있다.

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Safety Regulation of Enhanced In-Service Inspection(ISI) in Nuclear Power Plant (원자력발전소 강화 가동중검사 안전규제)

  • Shin, Ho-Sang
    • Journal of the Korean Society for Nondestructive Testing
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    • v.30 no.4
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    • pp.380-385
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    • 2010
  • The integrity of components and piping of operating nuclear power plants has been identified by in-service inspection(ISI) requirements and activities commensurate with standards and codes such as KEPIC MI or ASME Code Section XI. However, the other various degradation mechanisms not considered during design stage of nuclear power plants have been checked by enhanced ISI. The requirements of enhanced ISI have been voluntarily developed by the industry itself or strickly issued by regulatory body. Even though the requirements were developed by the industry, they should be reviewed by regulatory body for their application in nuclear power plants. The enhanced ISI activities and requirements of non-destructive examination(NDE) which reflect the degradation issues in nuclear power industry will be primarily discussed in this paper.

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.

Study on the Hydrogen Induced Cracking(HIC) Initiation of API-X80 Steels by Using 3-Axis Controlled Ultrasonic Inspection Unit (3축-초음파 비파괴 검사 장비를 이용한 API-X80 강재의 수소유기 균열 개시 연구)

  • Kim, Ma-Ro;Baek, Yeol;Choe, Yong
    • Proceedings of the Korean Institute of Surface Engineering Conference
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    • 2016.11a
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    • pp.202-202
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    • 2016
  • API X-80강재의 수소유기균열(HIC)현상을 비파괴적으로 평가하는 장치를 구축하고 금상학적 평가를 수행하였다. 시편은 열간 압연된 API X-80강재이며 평균입도는 약 $1.76-1.99{\mu}m$ 이었다. 압연재의 금상학적 집합조직은 (110)극점은 ND방향에 평행, (100)극점은 TD방향으로 약 $30^{\circ}$, TD방향으로부터 RD방향으로 약 $45^{\circ}$ 기울어져 있으며, (211)면은 RD방향에 수직인 면으로부터 TD방향으로 약 $35^{\circ}$ 기울어져서 있었다. Pin-on-disk형 마모시험기를 이용한 상온 평균 마찰계수는 0.745였으며 마모손실은 0.0196 mm/min 이었다. 3축 제어 초음파 비파괴 검사 장비는 표면으로부터 약 3mm 깊이의 1 mm 크기의 모의 균열을 탐촉자가 10 mm 접근하면 검출이 가능하였다. HIC시험분위기(NACE-standard TM 0248)에 1일 이상 장입하면 초음파비파괴검사장비로 측정될 수 있는 마이크로미터크기의 균열을 측정할 수 있었다.

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Review of Non-Destructive Evaluation Technologies for Rail Inspection (철도 레일의 결함 검출을 위한 비파괴탐상 기술)

  • Han, Soon-Woo;Cho, Seung-Hyun
    • Journal of the Korean Society for Nondestructive Testing
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    • v.31 no.4
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    • pp.398-413
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    • 2011
  • For railway safety, it is very important to detect damages of rails at their early stage because any undetected damage in a rail can break the rail and cause a serious railway accident. In this paper, several NDT applicable to rail inspections are described. Major damage types in rails are discussed first and the rail inspection technology using conventional piezoelectric ultrasonic transducers, which is widely adopted for damage detection of rails, is explained. Other NDT being researched or tested for rail inspection are also discussed as complementary technologies to the concurrent contact type ultrasonic inspection. Characteristics of each rail inspection technologies are evaluated in order to provide requirements for future development of a new rail inspection method.

Field Application of a Cable NDT System for Cable-Stayed Bridge Using MFL Sensors Integrated Climbing Robot (누설자속센서를 탑재시킨 이동로봇을 이용한 사장교 케이블 비파괴검사 시스템의 현장 적용)

  • Kim, Ju-Won;Choi, Jun-Sung;Lee, Eun-Chan;Park, Seung-Hee
    • Journal of the Korean Society for Nondestructive Testing
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    • v.34 no.1
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    • pp.60-67
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    • 2014
  • In this study, an automated cable non-destructive testing(NDT) system was developed to monitor the steel cables that are a core component of cable-stayed bridges. The magnetic flux leakage(MFL) method, which is suitable for ferromagnetic continuum structures and has been verified in previous studies, was applied to the cable inspection. A multi-channel MFL sensor head was fabricated using hall sensors and permanent magnets. A wheel-based cable climbing robot was fabricated to improve the accessibility to the cables, and operating software was developed to monitor the MFL-based NDT research and control the climbing robot. Remote data transmission and robot control were realized by applying wireless LAN communication. Finally, the developed element techniques were integrated into an MFL-based cable NDT system, and the field applicability of this system was verified through a field test at Seohae Bridge, which is a typical cable-stayed bridge currently in operation.

Comparison of Non-Destructive Testing Images using $^{192}Ir$ and $^{75}Se$ with Computed Radiography System (Computed Radiography 시스템에 $^{192}Ir$$^{75}Se$ 동위원소를 적용하여 촬영한 비파괴검사 영상 비교)

  • Kang, Sang-Mook;Chol, Chang-Il;Lee, Seung-Kyu;Park, Sang-Ki;Kim, Yong-Kyun
    • Journal of Radiation Protection and Research
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    • v.35 no.1
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    • pp.26-33
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    • 2010
  • A computed Radiography (CR) system by use of reusable Image Plate (IP) offers a convenient and reliable way to replace a conventional film-screen system for NDT (non-destructive testing) field. The quality of a radiography to detect a defect of welded objects depends on the procedure embracing several factors such as measurement conditions, image plate type/class, radiation energy, radiation type, and source to image plate distance. Also, the ability of images to detect a flaw reduces with increasing object thickness. In the study, the properties of gamma ray source were summarized for NDT field and inspection images of CR image system manufactured by FUJI were acquired using $^{75}Se$ and $^{192}Ir$ with welded objects. We analyzed the gray scale of hole defect image by using XCAP image processing program and calculated the image contrast and SNR in definition. Also the sesitivities of image quality indicator(IQI) were calculated for hot and cooling tube image of $^{75}Se$ and $^{192}Ir$.