• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 B
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• pp.1008-1010
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• 2005

In the examination of steam generator(SG) tube in nuclear power plant, eddy current testing probes play an important role in detecting the defects. Bobbin probe and MRPC probe is usually used for the inspection of SG tube. Bobbin probe is good at high speed inspection, but ability of detection of circumferential defect is very weak. On the contrary MRPC probe, which moves for inspection in the direction of axial and circumferential simultaneously, has very slow inspection speed, but it has excellent detection capability for small cracks, which is hardly detected by bobbin probe. In this paper, for the accurate analysis of experimental ECT signals, construction of MRPC probe signals database according to the variation of defect size is the main purpose. Using 3-D finite element method, ECT signals are analyzed, and signals analysis add according to frequency ingredient. The results, which are analysis and characteristics ion of electromagnetism simulation signals, is databased.

• Nuclear Engineering and Technology
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• 제41권1호
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• pp.125-134
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• 2009

This paper presents details on a tube inspection robotic system and a positioning method of the robot for a steam generator (SG) in nuclear power plants (NPPs). The robotic system is separated into three parts for easy handling, which reduces the radiation exposure during installation. The system has a supporting leg to increase the rigidity of the robot base. Since there are several thousands of tubes to be inspected inside a SG, it is very important to position the tool of the robot at the right tubes even if the robot base is positioned inaccurately during the installation. In order to obtain absolute accuracy of a position, the robot kinematics was mathematically modeled with the modified DH(Denavit-Hartenberg) model and calibrated on site using tube holes as calibration points. To tune the PID gains of a commercial motor driver systematically, the time delay control (TDC) based gain tuning method was adopted. To verify the performance of the robotic system, experiments on a Framatomes 51B Model type SG mockup were undertaken.

• 한국구조물진단유지관리공학회 논문집
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• 제11권3호
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• pp.143-150
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• 2007

본 연구에서는 카본시트튜브로 구속된 원형기둥에 반복 횡하중을 가하여 기둥의 휨내력을 평가하는 실험을 수행하였다. 중립축을 기준으로 압축 및 인장측 단면의 모멘트를 이용하여 공칭모멘트를 계산하는 등가응력블록계산법을 소개하였다. 또한 실험결과를 분석하여 횡 하중에 대한 거동을 예측할 수 있는 회귀식을 마련하여 실험결과와 비교하였다.

• 한국구조물진단유지관리공학회 논문집
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• 제10권3호
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• pp.152-159
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• 2006

본 연구에서는 카본시트튜브로 구속된 원형기둥의 성능을 평가하는 실험을 수행하였다. 일반적으로 기둥은 각형과 원형의 두 가지 형상으로 설계가 이루어지지만 단면의 전체가 일정한 곡률을 유지하여 구속효과가 큰 원형단면의 경우를 본 연구에서 채택하였다. 전체 17개의 시험체를 10,000kN 용량의 UTM을 이용하여 실험을 수행하여 극한강도를 예측하는 실험식을 제안하였다.

• 한국산학기술학회논문지
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• 제15권6호
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• pp.3376-3382
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• 2014

전자내시경을 이용하여 양극처리된 알루미늄 실린더튜브 내면의 결함을 자동으로 검사하는 시스템을 개발하였다. 이 시스템은 크게 자동 결함검사 소프트웨어, 전자내시경 및 이송장치 등으로 구성되어 있다. 실험을 통하여 자동 결함검사의 최적검출 조건을 도출하여 실린더튜브 내면의 결함 검사에 적용한 결과 주요 결함 요소인 스크래치, 산화물, 라인, 웰드라인의 인식률을 99%로서 만족하였다. 자동 결함검사 시스템을 생산현장에 적용하면 기존의 육안 검사 시 작업자가 가지는 육체적인 피로도 줄여 작업효율을 증가시키며, 결함검출 자료를 바탕으로 제품의 품질을 향상시킬 수 있다.

• 한국압력기기공학회 논문집
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• 제7권3호
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• pp.8-14
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• 2011

The clogging of the flow area at the tube support plates(TSPs), especially at the upper TSPs results in the water level oscillation of a steam generator during normal operation. A reduction of the TSP flow area causes to increase in pressure drop within the two-phase flow zone, which destabilizes the boiling flow through the tube bundle. This phenomenon was occasionally observed at a few domestic and foreign nuclear power plants. One of the methods for defining the flow area clogging is visual inspection, which is the most effective inspection method. The results of the visual inspection for TSPs' flow area are clogging images on TSPs' quartrefoil lobes. These images are complexly distorted due to lens aberration and external factors like the distance to a subject and angle etc. In this work, we developed the analysis algorithm for clogging image of the TSP flow area of steam generators. For this purpose, we designed an image verification device applicable to the camera employed in the field for visual inspection and then, we demonstrated the validity of image analysis algorithm by using this device and commercial autoCAD program.

• 품질경영학회지
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• 제29권3호
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• pp.124-137
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• 2001

In general, it is very efficient and effective to use screening variables that are correlated with the performance variable in case that measuring the performance variable is impossible (destructive) or expensive. The general methodology for searching surrogate variables is regression analysis. This paper considers the inspection problem in CRT (Cathode Ray Tube) production line, in which the performance variable (dependent variable) is binary type and screening variables are continuous. The general regression with dummy variable, discriminant analysis and binary logistic regression are considered. The cost model is also formulated to determine economically inspection procedure with screening variables.

• 한국구조물진단유지관리공학회 논문집
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• 제22권2호
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• pp.133-140
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• 2018

본 연구에서는 중공형의 PHC말뚝과 강관말뚝을 합성한 중공형 콘크리트 충전 강관(HCFT)말뚝의 거동분석을 위한 수치해석 모델을 개발하였고 휨강도시험에 적용하여 모델의 타당성을 검증하였다. 개발된 비선형 유한요소해석 모델의 적정성을 파악하기 위해 실물 시험 결과와 비교하였고 이를 활용하여 HCFT말뚝에 적합한 접촉조건, PC강봉의 제원에 따른 효과, 콘크리트 두께에 따른 효과 등을 분석하였다. 소성응력분배법을 적용하여 HCFT말뚝의 휨강도 산정식을 제안하였고 시험 및 해석결과와 비교하여 활용성을 검증하였다. 본 연구의 결과는 HCFT말뚝의 최적설계 및 거동분석에 기초자료로 활용될 수 있을 것으로 판단된다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2003년도 ICCAS
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• pp.772-777
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• 2003

A vision-based tool position estimation system for the inspection and maintenance manipulator working inside the steam generator bowl of nuclear power plants can help human operators ensure that the inspection probe or plug are inserted to the targeted tube. Some previous research proposed a simplified tube position verification system that counts the tubes passed through during the motion and displays only the position of the tool. In this paper, by using a general camera calibration approach, tool orientation is also estimated. In order to reduce the computation time and avoid the parameter bias problem in an ellipse fitting, a small number of edge points are collected around the large section of the ellipse boundary. Experiment results show that the camera calibration parameters, detected ellipses, and estimated tool position are appropriate.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2004년도 춘계 학술발표대회 개요집
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• pp.302-304
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• 2004

Nuclear fuel elements containing dry recycling nuclear fuel pellets for the irradiation test in a reactor were remotely fabricated from spent PWR fuel materials in a hot cell. End closure welding as well as seal tube welding for thermal sensor of the elements was performed by Nd:YAG laser. The soundness of the end closure welds and seal tube welds for the elements were evaluated by a precise X-ray inspection system composed of a micro-focus X-ray generator with an image intensifier and a real time camera system. Then, helium leak test was performed for the elements. The soundness of the welds of the fuel elements was confirmed by the X-ray inspection and helium leak test. The irradiation test for the fuel elements were successfully completed at the HANARO research reactor.