• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.465-470
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• 1996

본 연구는 원자로 RPV(Reactor Pressure Vessel)를 두 개의 이상적인 입체 구조물 즉, 원통면과 반구로 나누어, 원통면에서의 충격위치를 검출할 수 있는 알고리즘을 제안하고 그 효용성을 고찰하는데 있다. 현재 사용중인 원전내네 금속파편 감시계통(LPMS : Loose Parts Monitoring System)의 경우 충격신호를 레코더에 저장하고 전문가를 통해 데이터베이스화된 기준신호와 비교 분석하는 Off-line분석방법을 사용해 왔다. 그리나 이러한 방법은 많은 소요시간을 가지므로 손상잠재성이 큰 경우 즉각적인 대처를 할 수가 없다는 단점을 가진다. 따라서 본 논문에서는 이러한 방법을 지양하고 센서로부터 얻은 충격신호를 분석컴퓨터에 입력하여 즉각적으로 충격위치를 찾을 수 있는 On-line분석방법을 제안함에 있어, 기초적 연구로서 원통면에서의 충격위치 검출방법을 제시하였다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 1992년도 추계학술대회논문집; 반도아카데미, 20 Nov. 1992
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• pp.81-86
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• 1992

원자력발전소 1차 계통 내의 건전성 감시를 위한 설비로는 음향누설 감시계 통(Acoustic Leak Monitoring System: ALMS), 금속파편 감시계통(Loose Parts Monitoring System: LPMS) 및 원자로내부구조물 진동감시계통 (Internals Vibration Monitoring System: IVMS)등이 있다. 현재, 국내의 여 러 원전에는 이들중 일부 계통들이 선택적으로 설치되어 운전중이며, 영광 3,4호기에서는 국내 최초로 이들 3개의 계통을 종합한 핵증기공급계통 건전 성감시계통(Nuclear Steam Supply System Integrity Monitoring System: NIMS)을 설계하였다. 특히, 영광 3,4호기 NIMS에서는 각 계통에 의해 감지 된 1차 계통 내의 이상상태를 하나의 분석컴퓨터(Analysis Computer)를 사 용하여 해석하는 종합결함 탐지해석 기법을 도입하였다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2003년도 추계학술대회논문집
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• pp.361-364
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• 2003

The safe operation and reliable maintenance of nuclear power plants is one of the most fundamental and important tasks. It is known that a loose part such as a disengaged and drifting metal inside of reactor coolant systems might lead to a serious damage because of their impact on the components of the coolant system. In order to estimate the impact position of a loose par, three accelerometers attached to the wall of the coolant system have been used. These accelerometers measure the vibration of the coolant system induced by loose part impact. In the conventional analysis system, the low pass filtered version of the vibration data was used for the estimation of the position of a loose part. It is often difficult to identify the initial point of the impact signal by using just a low passed time signal because the impact wave is dispersed during propagation into the sensor. In this paper, the impact signal is analysed by use of various time frequency methods including the short time Fourier transform(STFT), the wavelet transform, and the Wigner-Vill distribution for finding a convenient way to identify the starting point of a impact signal and their advantages and limits are discussed.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2014년도 추계학술대회 논문집
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• pp.839-841
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• 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.

• 한국소음진동공학회논문집
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• 제26권4호
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• pp.469-474
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• 2016

Abnormal sound was heard from a heat exchanger of condensate water system in a nuclear power plant, which was identified as impact sound of a loose part later. Nuclear power plants are normally equipped with loose part monitoring system for primary water system, but not for secondary water system. The abnormal sound was analyzed by using the impact signal-processing methodology based on the Hertz theory. The predicted results for impact location and size of the loose part showed good agreement with those of the actual loose part found during the overhaul period in the plant. So, this analysis methodology for the impact signal will be widely utilized for the primary and secondary side of the nuclear power plant.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2006년도 춘계학술대회논문집
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• pp.1306-1311
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• 2006

The root cause of abnormal sound from a heat exchanger of condensate water system in a nuclear power plant is investigated by using the impact signal-processing methodology based on the Hertz theory. The predicted results for the location of impact force and the loose part size meet good agreement with the identified materials during the overhaul period in the plant. Nuclear power plants have experienced several loose parts and the frequency of the loose part will be increased along the aging of the plants. So, this analysis methodology for the impact signal will be widely utilized for the primary and secondary side of the nuclear power plant.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2006년도 춘계학술대회 논문집 전기기기 및 에너지변환시스템부문
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• pp.179-181
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• 2006

각 원자력 발전소에서는 정밀성, 안전성을 확인하는 검사의 중요성을 인식하여 LPMS(Loose Part Monitoring System)을 사용하여 사고 징후를 조기에 감지하여 이에 대한 예방조치를 가능케 함으로써 설계기준 사고 발생을 사전에 방지할 수 있게 한다. 또한 이 기술은 신호 측정 및 분석 등의 기반기술 개발을 통하여 건전성 감시 기술의 신뢰성을 향상 시키고 있다. LPMS(Loose Part Monitoring System)기술은 재료, 기기, 구조물 등의 성질과 내부조직을 변화시키거나 파괴하지 않고, 배관내부에 흐르는 금속 파편들을 찾아내어 정밀성, 안전성, 신뢰성을 확보하기 위하여 검사기술이 적용되고 있다. 그러나 이 방법은 배관내의 이물질의 충격이 발생해야 감지가 가능하고, 이물질의 모양이나 사이즈를 확인하기에는 어려움이 있다. 따라서 본 논문에서는 배관외부에서 자기장을 인가하여, 배관내의 이물질에 변화하는 자기장을 홀센서로 측정하여 기존의 LPMS 방식을 보완하는 시스템을 개발하기 위해, 배관에 필요한 자기장 발생장치를 설계하고, 이물질을 검출하기 위한 검출 감도향상에 대해 연구하였다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2014년도 추계학술대회 논문집
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• pp.181-184
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• 2014

Loose Parts Monitoring System(LPMS) monitors loosened or detached parts and foreign parts inside the pressure boundary of a reactor coolant system (RCS). It is difficult to discriminate valid signal from LPMS alarms at full power since the signal pattern by thermal shocks and structure friction are similar to those by loose metal impacts. In addition, It is more difficult to discriminate the impact signals induced by the rod driving, sensor hard-line movement and loosened component since they have similar frequency characteristics with valid signals. This paper classifies the signal patterns by analyzing actual LPMS signal captured during nuclear power plant operation.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2008년도 추계학술대회논문집
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• pp.687-692
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• 2008

In a nuclear power plant, loose part monitoring and its diagnostic technique is one of the major issues for ensuring the structural integrity of the reactor system. Typically, accelerometers are mounted on the surface of a reactor vessel to localize impact location caused by the impact of metallic substances on the reactor system. However, in some cases, the number of the accelerometers is not enough to estimate the impact location precisely. In such a case, one of alternative plan is to utilize another type sensors that can measure the vibration of the reactor structure even though the measuring frequency ranges are different from each others. The AE sensors installed on the reactor structure can be utilized as additional sensors for loose part monitoring. In this paper, we proposed a new method to estimate impact location by using both accelerometer signal and AE signal, simultaneously. The feasibility of the proposed method is verified by an experiment. The experimental results demonstrate that we can enhance the reliability and precision of the loose part monitoring.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2000년도 춘계학술대회논문집
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• pp.670-678
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• 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.