• Title/Summary/Keyword: 비파괴 검사주기

Search Result 49, Processing Time 0.028 seconds

Development of Tube Quality Trend Analysis System using Non-Destructive Testing Information (비파괴검사정보를 활용한 Tube 건전성 추이분석 시스템 개발)

  • Shin, Jin-Ho;Song, Jae-Ju;Jang, Mun-Jong
    • Proceedings of the KIEE Conference
    • /
    • 2001.10a
    • /
    • pp.224-226
    • /
    • 2001
  • 원자력발전소에서는 수많은 Tube로 구성된 증기발생기와 열교환기를 정기적으로 와전류를 이용하여 비파괴검사를 수행한다. 와전류는 재료의 재질, 결함, 이종금속, 형상변화 등에 의해 그 발생상태가 다르기 때문에 검출용 코일에서 얻어진 신호성분을 해석함으로써 재료의 비파괴검사가 가능하다. 본 논문에서는 비파괴검사정보를 추출하고 변환 처리하는 과정과 비파괴검사정보를 Tubesheet에 Mapping 처리하는 기능, 검사주기 및 기기별로 비파괴검사정보를 비교 분석할 수 있는 기능, 하나의 Tube에 대한 결함깊이별, 결함진폭별 결함성장률 현황 등 Tube의 건전성을 평가할 수 있는 추이분석 자료를 제공하는 시스템의 설계와 구현에 대한 개발 결과를 소개한다.

  • PDF

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
    • /
    • v.31 no.4
    • /
    • pp.398-413
    • /
    • 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.

Nondestructive Examination of PHWR Pressure Tube Using Eddy Current Technique (와전류검사 기술을 적용한 가압중수로 원전 압력관 비파괴검사)

  • Lee, Hee-Jong;Choi, Sung-Nam;Cho, Chan-Hee;Yoo, Hyun-Joo;Moon, Gyoon-Young
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.34 no.3
    • /
    • pp.254-259
    • /
    • 2014
  • A pressurized heavy water reactor (PHWR) core has 380 fuel channels contained and supported by a horizontal cylindrical vessel known as the calandria, whereas a pressurized water reactor (PWR) has only a single reactor vessel. The pressure tube, which is a pressure-retaining component, has a 103.4 mm inside diameter ${\times}$ 4.19 mm wall thickness, and is 6.36 m long, made of a zirconium alloy (Zr-2.5 wt% Nb). This provides support for the fuel while transporting the $D_2O$ heat-transfer fluid. The simple tubular geometry invites highly automated inspection, and good approach for all inspection. Similar to all nuclear heat-transfer pressure boundaries, the PHWR pressure tube requires a rigorous, periodic inspection to assess the reactor integrity in accordance with the Korea Nuclear Safety Committee law. Volumetric-based nondestructive evaluation (NDE) techniques utilizing ultrasonic and eddy current testing have been adopted for use in the periodic inspection of the fuel channel. The eddy current testing, as a supplemental NDE method to ultrasonic testing, is used to confirm the flaws primarily detected through ultrasonic testing, however, eddy current testing offers a significant advantage in that its ability to detect surface flaws is superior to that of ultrasonic testing. In this paper, effectiveness of flaw detection and the depth sizing capability by eddy current testing for the inside surface of a pressure tube, will be introduced. As a result of this examination, the ET technique is found to be useful only as a detection technique for defects because it can detect fine defects on the surface with high resolution. However, the ET technique is not recommended for use as a depth sizing method because it has a large degree of error for depth sizing.

Evaluation of Non Destructive Inspection Interval for Running Safety of Railway Axle (철도차량 안전성을 위한 주행 차축의 비파괴 검사주기 평가)

  • Kwon, Seok Jin;Lee, Dong Hyung;Seo, Jung Won;Kim, Jae Chul
    • Journal of the Korean Society for Precision Engineering
    • /
    • v.31 no.9
    • /
    • pp.777-782
    • /
    • 2014
  • Usually, railway axles are designed for infinite life based on endurance limit of the material and the axle is not fractured immediately when a surface crack initiated. The railway axles have been inspected regularly by NDT such as ultrasonic testing, magnetic testing and eddy current testing and so on. Because the axle failure is profoundly influenced by the probability of missing a fatigue crack during an NDT inspection, it is necessary to evaluate the Non Destructive Interval of railway axle. In the present paper, the Non Destructive Interval of railway axle based on fracture mechanics and finite element analysis was investigated. It was shown that the Non Destructive Interval of railway axle can be evaluated using fracture mechanics approach and extended using NDT which a crack can detect clearly.

Development and Application of Photoacoustic Microscope using Accelerometer (가속도센서를 이용한 광음향현미경의 제작과 응용)

  • Kim, D.H.;Kwon, Oh-Yang
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.14 no.4
    • /
    • pp.219-227
    • /
    • 1995
  • A two-dimensional photoacoustic microscope utilizing photoacoustic signals generated by periodic heating of specimen surface with Argon ion laser and measured by accelerometer has been developed. Several aluminum specimens with various defects have been examined, characteristics of the microscope have been evaluated and optimal experimental conditions have been determined by examining the dependence on several experimental conditions including the modulation frequency and the beam width of laser.

  • PDF

ISI NDE Total Support System for Korean Nuclear Power Plants (원전 가동중검사 종합지원체계)

  • Jeong, Yi-Hwan Peter
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.18 no.4
    • /
    • pp.321-329
    • /
    • 1998
  • Structural integrity of nuclear components is important for a safe operation of nuclear power plants. Therefore, nuclear power plants require to perform reliable, periodic inservice inspections. Korea Electric Power Company(KEPCO) operates the entire Korean nuclear power plants. Since nuclear power plant safety and the associated inservice inspection(ISI) are under the plant owner's responsibility, Korea Electric Power Research Institute(KEPRI), the R&D division of KEPCO, has established the ISI NDE Total Support system(TSS) for an efficient performance of ISI tasks, and initiated both key ISI NDE technology development program and traing & qualification system development program for an independent ISI operation. This paper describes details of these programs.

  • PDF

Development of LabVIEW Program for Lock-In Infrared Thermography (위상잠금 열화상장치 제어용 랩뷰 프로그램 개발)

  • Min, Tae-Hoon;Na, Hyung-Chul;Kim, Noh-Yu
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.31 no.2
    • /
    • pp.127-133
    • /
    • 2011
  • A LabVIEW program has been developed together with simple infrared thermography(IRT) system to control the lock-in conditions of the system efficiently. The IR imaging software was designed to operate both of infrared camera and halogen lamp by synchronizing them with periodic sine signal based on thyristor(SCR) circuits. LabVIEW software was programmed to provide users with screen-menu functions by which it can change the period and energy of heat source, operate the camera to acquire image, and monitor the state of the system on the computer screen. In experiment, lock-in IR image for a specimen with artificial hole defects was obtained by the developed IRT system and compared with optical image.

Comparative Study on the Technical Standards for the In-Service Inspection of Nuclear Power Plant Components in Several Countries (원전의 가동중검사 관련 각국의 기술기준 비교고찰)

  • Shin, Ho-Sang;Kim, Kyung-Jo;Jang, Chang-Heui;Kang, Suk-Chull
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.24 no.2
    • /
    • pp.186-196
    • /
    • 2004
  • In each country, the periodic ISI(In-Service Inspection) is required by the law to protect the public health and property from the potential accident of the nuclear facilities. To support the implementation of ISI program, the prescriptive ISI technical standards have been established. As the key parts of the ISI program, the non-destructive examination techniques are widely used to identify the degree of degradation of the pressure boundary components and welds. Recently, the risk informed-ISI program has been developed and implemented in several countries. Nonetheless, the existing ISI program which prescriptively decides the scope of inspection still has its own significance. In this article, the technical standards of ISI in leading countries like US, france, Canada, and Japan are reviewed and compared with the safety guide by IAEA. An outline to revise the domestic technical standards of ISI has been suggested.

The Experience of Inservice Inspection for Yonggwang Nuclear Power Plant Unit 6 (영광 원자력발전소 6호기 가동중검사 수형 경험)

  • Kim, Young-Ho;Nam, Min-Woo;Yang, Seung-Han;Yoon, Byung-Sik;Kim, Yong-Sik
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.24 no.4
    • /
    • pp.384-389
    • /
    • 2004
  • As the increase of the operation year of nuclear power plants, the probabilities of the degradation of the major facilities and materials in the nuclear power plants are increased. The integrity of those facilities shall be monitored and verified by the non-destructive examination methods with the regulation codes, so called inservice inspection(ISI). The ISI of Yonggwang unit 6 was performed in four different parts, 1) non-destructive examinations for the components, piping weldments and structures, 2) automated ultrasonic examinations for pressure vessels, 3) visual examinations for the interior structures of the reactor, 4) eddy current examinations for the steam generator tubes. As the results, there was no severe indication and all detected indications were evaluated as non-relavent. Especially for the examinations of the piping weldments, PD(Performance Demonstration) was applied as a W examination method defined in the 1995 edition of ASME Code Sec. XI. The implementation of the PD for the piping weld results in an improvement of the reliability of the UT examinations.

Feasibility Study on Detection of Crack in Bovine Incisor Using Active Thermography (보빈 치아 균열의 적외선 열화상 검사 가능성에 관한 실험적 연구)

  • Kim, Woo-Jae;Yang, Seung-Yong;Kim, No-Hyu
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.31 no.5
    • /
    • pp.508-515
    • /
    • 2011
  • Bovine incisor was investigated using active infrared thermography(IRT) to visualize crack on bovine teeth. An artificial crack was carefully created in bovine incisor sample by compression load of universal tensile machine. While applying a sinusoidal heat wave to the cracked bovine incisor through halogen lamp, consecutive digital infrared images was captured from the sample surface at a frequency synchronized with heat excitation. Phase information of thermal image was calculated by four-point correlation method and processed to produce the phase image of bovine incisor. This phase image showed clearly the crack on the incisor, which was hardly detected in traditional passive thermography.