• 제목/요약/키워드: Loose Parts

검색결과 81건 처리시간 0.032초

고해상도 센서어레이 신호처리법을 이용한 원자력발전소 핵증기 공급계통의 새로운 금속파편 진단기법 (A New Loose Parts Monitoring Technique for Nuclear Steam Supply System based on High Resolution Sensor Array Signal Processing)

  • 이일근;최재원
    • 한국음향학회지
    • /
    • 제16권6호
    • /
    • pp.76-84
    • /
    • 1997
  • 원전내 금속파편들을 조기에 탐지하기 위한 금속파편 감시계통(LPMS : Loose Parts Monitoring System)은 원전의 안전성 및 신뢰도 확보를 위하여 중요한 부분으로서, 대부분의 국내 원전들에서 설치 운영중이거나 운영예정이다. 하지만 이들 LPMS들은 외국에서 개발된 것들로서 고가이며 기술이전이 이루어지지 않아 기술종속의 우려와 함께 효과적인 금속파편 진단에 많은 어려움을 지닌다. 따라서 본 논문의 주된 목적은 고해상도를 가지며 분석방법이 간단한 효율적인 금속파편 위치평가를 위한 알고리즘을 제안, 실현하므로써, 빈전문적인 운전자도 컴퓨터를 사용한 간단한 조작을 통하여 정확하고 신속한 금속파편 진단을 수행할 수 있도록 하는 것이다. 본 논문에서 제안한 수정된 원교차법을 이용하여 작성된 금속파편 위치평가 프로그램을 이용하여 실제 원전상황을 고려한 모의실험을 실시한 결과, 제안된 평가기법이 약 3.4% 정도 오차를 가지는 우수한 위치평가를 수행함을 알 수 있었다.

  • PDF

SG전열관 2차측 이물질 검출 및 특성분석을 위한 ETSS 개발 (Development of ETSS for the SG Secondary Side Loose Part Signal Detection and Characterization)

  • 신기석;문용식;민경만
    • 한국압력기기공학회 논문집
    • /
    • 제7권3호
    • /
    • pp.61-66
    • /
    • 2011
  • The integrity of the SG(Steam Generator) tubes has been challenged by numerous factors such as flaws, operation, atmosphere, inherently degraded materials, loose parts and even human errors. Of the factors, loose parts(or foreign materials) on the secondary side of the tubes can bring about volumetric defects and even leakage from the primary to the secondary side in a short period of time. More serious concerns about the loose parts are their unknown influx path and rapid growth rate of the defects affected by the loose parts. Therefore it is imperative to detect and characterize the foreign materials and the defects. As a part of the measures for loose part detection, TTS(Top of Tubesheet) MRPC(Motorized Rotating Pancake Coils) ECT has been carried out especially to the restricted high probability area of the loose part. However, in the presence of loose parts in the other areas, wide range loose part detection techniques are required. In this study, loose part standard tube was presented as a way to accurately detect and characterize loose part signals. And the SG tube ECT bobbin coil and MRPC ISI(In-service Inspection) data of domestic OPR-1000 and Westinghouse Model F(W_F) were reviewed and consequently, comprehensive loose part detection technique is derived especially by applying bobbin coil signals

국내 원전의 금속파편 감시기술 및 설비 현황 (Status of Loose Part Monitoring Technology and Facility in Domestic Nuclear Power Plant)

  • 김태룡;이준신;손석만
    • 한국소음진동공학회:학술대회논문집
    • /
    • 한국소음진동공학회 2000년도 춘계학술대회논문집
    • /
    • pp.670-678
    • /
    • 2000
  • Loose parts monitoring system(LPMS) is one of the important monitoring systems for the safe and efficient operation of the nuclear reactor, since it is LPMS that can early detect loose parts which may cause a significant damage in facilities or components of the plant. Nuclear power plants in Korea have recently experienced several loose part alarms due to the metallic impact and it is expected that the frequency of the loose part will be increased along the aging of the plants. In this paper, the status of loose parts monitoring technologies and facilities in Korean nuclear power plants is presented for the establishment of LPMS installation plan in some nuclear reactors which are not yet equipped with LPMS. Sensor specification, location and mounting method for loose parts monitoring were reviewed. As a result, the location and the mounting method of the properly chosen sensor was recommended. Data acquisition algorithms and discriminating rules of loose part impact signals were also reviewed. Actual alarm cases occurred by true impact signal and false impact signal were stated here.

  • PDF

금속파편 충격 신호분석을 위한 굽힘파의 거리 감쇠 (Distance Attenuation of Bending Wave to Analyze the Loose Parts Impact Signal)

  • 이정한;박진호
    • 한국소음진동공학회논문집
    • /
    • 제26권5호
    • /
    • pp.594-601
    • /
    • 2016
  • Mass estimation analysis of loose-parts in pressure vessel is necessary for the structural integrity assessment of pressure boundary in nuclear power plants. Mass of loose-parts can be generally estimated from the peak values and the center frequency of impact signals. Magnitude of impact signals is, however, inevitably attenuated according to the traveling distance of the signals and depending on the frequencies. Attenuation rate must be therefore carefully compensated for the precise estimation of loose-part mass. This paper proposes a new compensation method for the attenuation rate based on Bessel function instead of Hankel function in conventional method which has a limitation of usage in near the impact location. It was verified that the suggested compensating equation based on the Bessel function can be applied to the attenuation rate calculation without any limitation.

Impact parameter prediction of a simulated metallic loose part using convolutional neural network

  • Moon, Seongin;Han, Seongjin;Kang, To;Han, Soonwoo;Kim, Kyungmo;Yu, Yongkyun;Eom, Joseph
    • Nuclear Engineering and Technology
    • /
    • 제53권4호
    • /
    • pp.1199-1209
    • /
    • 2021
  • The detection of unexpected loose parts in the primary coolant system in a nuclear power plant remains an extremely important issue. It is essential to develop a methodology for the localization and mass estimation of loose parts owing to the high prediction error of conventional methods. An effective approach is presented for the localization and mass estimation of a loose part using machine-learning and deep-learning algorithms. First, a methodology was developed to estimate both the impact location and the mass of a loose part at the same times in a real structure in which geometric changes exist. Second, an impact database was constructed through a series of impact finite-element analyses (FEAs). Then, impact parameter prediction modes were generated for localization and mass estimation of a simulated metallic loose part using machine-learning algorithms (artificial neural network, Gaussian process, and support vector machine) and a deep-learning algorithm (convolutional neural network). The usefulness of the methodology was validated through blind tests, and the noise effect of the training data was also investigated. The high performance obtained in this study shows that the proposed methodology using an FEA-based database and deep learning is useful for localization and mass estimation of loose parts on site.

원전 금속이물질 감시계통 센서 플레이트의 진동 특성 개선 연구 (Improvement of Vibration Response of a Sensor Plate of Loose Parts Monitoring System in Nuclear Power Plants)

  • 서정석;한순우;이정한;강토;박진호
    • 한국소음진동공학회논문집
    • /
    • 제27권2호
    • /
    • pp.148-154
    • /
    • 2017
  • This paper discussed design for resonance avoidance of sensor plates of loose-parts monitoring systems (LPMS) in nuclear power plants (NPP). An LPMS monitors impact of loose parts in primary loop of NPP by using accelerometers, which is mounted on sensor plates. Resonance of the plates may cause false alarms at frequencies over 10 kHz, which can be misunderstood as impact signals of loose parts with small mass and cause unnecessary response of NPP operators. Modal analysis was carried out for the existing sensor plate and design parameters affecting natural frequencies were chosen. Frequency response functions of plates were analyzed by changing the parameters and the optimized plate design for avoiding resonance was determined. Experiments was carried out for the plate specimen with improved design and verified the proposed approach and design.

Model-based localization and mass-estimation methodology of metallic loose parts

  • Moon, Seongin;Han, Seongjin;Kang, To;Han, Soonwoo;Kim, Munsung
    • Nuclear Engineering and Technology
    • /
    • 제52권4호
    • /
    • pp.846-855
    • /
    • 2020
  • A loose part monitoring system is used to detect unexpected loose parts in a reactor coolant system in a nuclear power plant. It is still necessary to develop a new methodology for the localization and mass estimation of loose parts owing to the high estimation error of conventional methods. In addition, model-based diagnostics recently emphasized the importance of a model describing the behavior of a mechanical system or component. The purpose of this study is to propose a new localization and mass-estimation method based on finite element analysis (FEA) and optimization technique. First, an FEA model to simulate the propagation behavior of the bending wave generated by a metal sphere impact is validated by performing an impact test and a corresponding FEA and optimization for a downsized steam-generator structure. Second, a novel methodology based on FEA and optimization technique was proposed to estimate the impact location and mass of a loose part at the same time. The usefulness of the methodology was then validated through a series of FEAs and some blind tests. A new feature vector, the cross-correlation function, was also proposed to predict the impact location and mass of a loose part, and its usefulness was then validated. It is expected that the proposed methodology can be utilized in model-based diagnostics for the estimation of impact parameters such as the mass, velocity, and impact location of a loose part. In addition, the FEA-based model can be used to optimize the sensor position to improve the collected data quality in the site of nuclear power plants.

An Automatic Diagnosis Methods for Impact Location Estimation

  • 김정수;류준
    • 전기전자학회논문지
    • /
    • 제3권1호
    • /
    • pp.101-108
    • /
    • 1999
  • 본 논문은 금속파편이 발생시 금속파편의 위치를 추정하기위한 위치 추정 알고리즘을 제안한다. 이 추정 알고리즘은 자동화된 알람 구별부와 위치 추정부로 구성된다. 알람 구별부는 충격 신호인지 거짓 충격 신호인지를 구별하는 기능을 수행하며, 위치 추정부는 충격신호로부터 충격신호의 시작점을 찾아내어 위치를 추정한다. 이 알고리즘의 타당성을 검증하기위해 원자로 Mock-up 상에서 실험한 결과 위치 추정값 과 실제 충격값이 약 10 % 이내의 오차율을 보였다.

  • PDF

Development of a Mass Estimation Algorithm Using the Impact Test Data of Nuclear Power Plant

  • Kim, J.S.;I.K. Hwang;Lee, D.Y.;C.S. Ham;Kim, T.H.
    • Nuclear Engineering and Technology
    • /
    • 제32권3호
    • /
    • pp.227-234
    • /
    • 2000
  • It is known that loose parts in the reactor coolant system (RCS) cause serious damage to the systems. This paper is concerned with estimating the mass of a loose part in the steam generator of a nuclear power plant. We developed the mass estimation algorithm based on the Hertz theory in order to estimate the mass of the loose parts and applied the algorithm to the impact test data of YGN3. The mass estimation values were compared with real values in order to verify the algorithm. The result showed that the average error of the mass estimation value is less than 27%.

  • PDF

LPMS 신호분석 연구 (A Study on the Signal Analysis of Loose Parts Monitoring System)

  • 이상국
    • 한국소음진동공학회:학술대회논문집
    • /
    • 한국소음진동공학회 2014년도 추계학술대회 논문집
    • /
    • pp.839-841
    • /
    • 2014
  • The Nuclear Steam Supply System(NSSS) is designed to provide an integrated approach that includes areas of monitoring relevant to the integrity of the NSSS. LPMS is designed to function as an alarm system by providing sensor channel alarms for the associated subsystems. LPMS is equipped to provide analysis tools for new alarm events, historical events and for historical periodically stored channel data (e.g. waveforms) for most channels. This paper is intended to introduce the diagnosis principle and abnormal symptom of loose parts monitoring system as a monitoring tool in Nuclear Steam Supply System. And also, we are going to introduce signal analysis program in order to perform the actual diagnosis in power plants.

  • PDF