• Corrosion Science and Technology
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• 제12권3호
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• pp.142-148
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• 2013

Safety is a major concern in Nuclear Power Plants (NPPs). Piping systems in NPPs are very complex and composed of many components such as tees, elbows, expanders and straight pipes. The high pressure and high temperature water flows inside piping components. As high speed water flows inside piping, the pipe wall thinning occurs in various reasons such as FAC (Flow Accelerated Corrosion), LDIE (Liquid Droplet Impingement Erosion) and Flashing. To inspect the wall thinning phenomenon and protect the piping from damages, piping components are checked by UT measurement in every overhaul. During every overhaul, approximately 200~300 components (40,000~60,000 UT data) are examined in NPPs. There are some methods from EPRI for evaluating wear rate of components. However, only few studies have been conducted to find out the raw data reliability for the wear rate evaluation. Securing the reliable raw data is the key factor for a reasonable evaluation. This paper suggests the reliability analysis method for the repeatedly measured data for wear rate evaluation.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회A
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• pp.120-125
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• 2007

Put Abstract text here The strain distribution measurement for wall thinned pipe bends by ESPI is presented. Defect types observed in the steel piping in the nuclear power plants (NPP) are the crack at the weld part and the wall thinning defect in the pipe bends. Especially, the wall thinning defects in the pipe bends due to the flow-accelerated corrosion (FAC) is a main type of defects observed in the carbon steel piping system. ESPI is one of the optical non-destructive testing methods and can measure the stress and the strain distribution of the object subjected by the tensile loading or the internal pressure. In this paper, the strain distribution of the wall thinned pipe bends due to the internal pressure will be measured by ESPI technique and the results are discussed. From the results, the size of the wall thinning defect can also be measured approximately.

• Nuclear Engineering and Technology
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• 제42권5호
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• pp.546-551
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• 2010

The objective of this research is to estimate the crack location and size of a carbon steel pipe by using a laser ultrasound guided wave for the wall thinning evaluation of an elbow. The wall thinning of the carbon steel pipe is one of the most serious problems in nuclear power plants, especially the wall thinning of the carbon steel elbow caused by Flow-Accelerated Corrosion (FAC). Therefore, a non-destructive inspection method of elbow is essential for the nuclear power plants to operate safely. The specimens used in this study were carbon steel elbows, which represented the main elements of real nuclear power plants. The shape of the wall thinning was an oval with a width of 120mm, a length of 80mm, and a depth of 5mm. The L(0,1) and L(0,2) modes variation of the ultrasound guided wave signal is obtained from the response of the laser generation/air-coupled detection ultrasonic hybrid system represent the characteristics of the defect. The trends of these characteristics and signal processing were used to estimate the size and location of wall thinning.

• 설비공학논문집
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• 제23권7호
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• pp.483-491
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• 2011

When pipe components made of carbon steel in nuclear, fossil, and industry are exposed to flowing fluid, wall thinning caused by FAC(flow accelerated corrosion) can be generated and eventually ruptured at the portion of pressure boundary. A study to identify the locations generating local wall thinning and to disclose turbulence coefficient related to the local wall thinning was performed. Experiment and numerical analyses for tee of down scaled piping components were performed and the results were compared. In particular, flow visualization experiment which was used alkali metallic salt was performed to find actual location of local wall thinning inside tee components. To disclose the relationship between turbulence coefficients and local wall thinning, numerical analyses were performed for tee components. The turbulence coefficients based on the numerical analyses were compared with the local wall thinning based on the measured data. From the comparison of the results, the vertical flow velocity component(Vr) flowing to the wall after separating in the wall due to the geometrical configuration and colliding with the wall directly at an angle of some degree was analogous to the configuration of local wall thinning.

• Corrosion Science and Technology
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• 제12권5호
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• pp.227-232
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• 2013

A number of components installed in the secondary system of nuclear power plants are exposed to aging mechanisms such as FAC (Flow-Accelerated Corrosion), Cavitation, Flashing, and LDIE (Liquid Droplet Impingement Erosion). Those aging mechanisms can lead to thinning of the components. In April 2013, one (1) inch small bore piping branched from the main steam line experienced leakage resulting from wall thinning in a 1,000 MWe Korean PWR nuclear power plant. During the normal operation, extracted steam from the main steam line goes to condenser through the small bore piping. The leak occurred in the downstream of an orifice. A control valve with vertical flow path was placed on in front of the orifice. This paper deals with UT (Ultrasonic Test) thickness data, SEM images, and numerical simulation results in order to analyze the extent of damage and the cause of leakage in the small bore piping. As a result, it is concluded that the main cause of the small bore pipe wall thinning is liquid droplet impingement erosion. Moreover, it is observed that the leak occurred at the reattachment point of the vortex flow in the downstream side of the orifice.

• Corrosion Science and Technology
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• 제14권1호
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• pp.19-24
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• 2015

지금까지 마그네타이트 전극의 제조 방법과 전기화학적 특성에 대해 살펴보았다. 마그네타이트 전극을 제조하는 방법은 프레스법, 페이스트법, 전기도금법 등이 있으며, 이들의 전기화학 특성은 다음과 같이 정리할 수 있다. 1. Cycle voltammetry 실험을 통하여 애노딕, 캐소딕 분극 방향으로 각각 2개의 peak가 관찰되고, 이것은 $Fe_3O_4$가 $Fe(OH)_2$, FeO 등의 중간 산화물 형태를 거쳐 $Fe^{2+}$로 용해되는 반응들이다. 2. 산성 및 중성 용액에서는 마그네타이트의 환원적 용해가, 염기성 용액에서는 헤마타이트로의 산화 반응이 나타난다. 3. 전기화학 실험 결과와 마그네타이트 용해도를 관련시키기 위해서는 마그네타이트 용해가 일어나는 전위에서 실험 후, 용액에서 $Fe^{2+}$, $Fe^{3+}$ 이온들에 대한 분석이 필요하다.

• 플랜트 저널
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• 제15권1호
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• pp.25-30
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• 2019

본 연구에서는 배관 곡관부의 유동가속부식을 일으키는 인자 중 수력학적 인자인 유동형태 변경에 따른 영향을 분석하고 부식을 저감시키는 연구를 추진하였다. 열전달과 물질전달, 물질전달과 유동가속부식의 상사성에 대해 이론적 분석을 통해 확인하고 상용 수치해석 프로그램을 이용하여 국소대류열전달계수를 해석함으로써 곡관부의 물질전달 특성에 대해 고찰하였다. 곡관부 상류의 직관부 내표면 안쪽과 바깥쪽에 요철을 설치하였을 때 최대 국소열전달계수는 기본유동에 비하여 현저히 감소하여 요철의 위치와 형태에 따라 차이가 있으나 24.9%까지 감소함을 확인하였으며, 곡관부 상류의 직관부에 가인드 베인을 삽입하면 가이드 베인에 의한 배관 내측면적 크기에 따라 차이가 있으나 최대 국소열전달계수가 기본유동에 비해 12.5%까지 감소함을 확인하였다.

• Corrosion Science and Technology
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• 제13권2호
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• pp.62-69
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• 2014

A huge number of carbon steel piping components installed in the secondary system of nuclear power plants are exposed to aging mechanisms such as FAC (Flow-Accelerated Corrosion), Cavitation, Flashing, and LDIE (Liquid Droplet Impingement Erosion). Those aging mechanisms can lead to thinning of the piping components. To manage the wall thinning degradation, most of utilities in the world predict the wall thinning rate based on the computational program such as CHECWORKS, COMSY, and BRT-CICERO, evaluate the UT (Ultrasonic Test) data, and determine next inspection timing, repair or replacement, if needed. There are several evaluation methods, such as band, blanket, and strip methods, commonly used for determining the wear of piping components from single UT inspection data. It has been identified that those single UT evaluation methods not only do not consider the manufacturing features of pipes, but also may exclude the data of the most thinned point when determining the representative wear rate of piping components. This paper describes a newly developed single UT evaluation method, E-Cross method, for solving above problems and introduces application examples for several pipes and elbows. It was identified that the E-Cross method using the length and width of UT data excluded the most thinned points appropriate as the single UT evaluation method for thinned piping components.

• 대한기계학회논문집A
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• 제29권7호
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• pp.947-954
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• 2005

The purpose of this study is to develop failure pressure evaluation models, which are applicable to straight pipes and elbows containing an internally wall thinning defect induced by flow-accelerated-corrosion (FAC). In this study, thus, three dimensional finite element (FE) analyses are performed to investigate the dependences of failure pressure of internally wall thinned pipe on the defect shape, the pipe geometry, and the defect location and bend radius of elbow. Also, the existing failure pressure assessment models for externally wall thinned pipes are examined. Based on these, the new models for assessing failure pressure of piping components with an internally wall thinning defect are proposed. Comparison of failure pressure, predicted by proposed models, with FE analysis result shows good agreement regardless of pipe type, defect shape, and defect location and bend radius.

• 비파괴검사학회지
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• 제28권2호
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• pp.191-198
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• 2008

유체가속부식에 의한 탄소강 배관의 감육은 원자력 발전소 저탄소강 배관의 주요 경년열화 현상으로서, 예상치 못한 배관의 파단을 야기해 발전소의 성능 및 안전을 저해할 수 있다. 최근, 등전위 교번식 직류 전위차법(ES-DCPD, equipotential switching direct current potential drop)을 이용한 배관 감육의 정밀 감시기법이 본 연구자들에 의하여 개발되었다. ES-DCPD 방법은 넓은 배관 영역을 빠르게 검사할 수 있는 방법으로, 넓은 영역의 직관부 감육을 빠르게 검사하는 광역감시법(WiRN, wide range monitoring)과 엘보우 등 곡관부의 감육이 활발한 컴포넌트의 국부적 감육을 비교적 넓은 범위에서 빠르게 스캔하는 협역감시법(NaRM, narrow range monitoring)으로 사용이 가능하다. 광역감시와 협역감시 기법은 초음파검사의 위치 선정파 초음파검사의 검사 누락부에 대한 신뢰성을 개선할 수 있을 것이다. 본 논문에서는 ES-DCPD를 바탕으로 한 새로운 감육 진단 기술을 실험실 환경에서 장기 검증 시험을 수행하여 신호 정밀도를 분석하였고, 결과의 현장 적용성을 논의하였다.