• 제목/요약/키워드: Wall-Thinning

검색결과 271건 처리시간 0.027초

원전감육배관 UT 두께측정 결과의 신뢰도 평가를 위한 다자비교시험 (Round Robin Test for Reliability Evaluation of Ultrasonic Thickness Measurement Results in Nuclear Power Plant Pipelines)

  • 이승준;이원근;이준현;이성호
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회A
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    • pp.1702-1707
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    • 2007
  • The reduction of pipe-thickness induced by flow accelerated corrosion (FAC) is one of the most serious problems on the maintenance of piping system in nuclear power plants (NNP). If the thickness of a pipe component is reduced below the critical level, it cannot sustain pressure and consequently results in leakage or rupture. For this reason, wall thinning by FAC has been inspected in secondary side piping systems in NPPs. In this research Round Robin Test (RRT) was conducted to verify confidence of wall thinning measurement system in NPP. 12 inspectors from 3 companies participated and 23 specimens were used according to standard practice in RRT. The gage R&R analysis was introduced in regard to repeatability and reproducibility that are affected to measurement system errors. Confidence intervals of thickness measurement system were obtained.

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고압형 급수가열기 동체 감육 완화를 위한 추기노즐 주변의 유동특성 연구 (A Study on the Flow Characteristic of surroundings of the Extracting Nozzle for Shell Wall Thinning of a Feedwater Heater)

  • 서혁기;김윤신;김경훈;황경모
    • 대한설비공학회:학술대회논문집
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    • 대한설비공학회 2009년도 하계학술발표대회 논문집
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    • pp.841-846
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    • 2009
  • Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction stream line inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. This paper describes operation of experience and numerical analysis composed similar condition with real high pressure feedwater heater. This study applied several impingement baffle plates to feedwater heater same as previous study. In addition, it shows difference of pressure distribution and value between single phase and two phase based on experience and numerical analysis.

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Evaluation of Piping Integrity in Thinned Main Feedwater Pipes

  • Park, Young-Hwan;Kang, Suk-Chull
    • Nuclear Engineering and Technology
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    • 제32권1호
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    • pp.67-76
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    • 2000
  • Significant wall thinning due to flow accelerated corrosion(FAC)was recently reported in main feedwater pipes in 3 Korean pressurized water reactor(PWR) plants. The main feedwater pipes in one plant were repaired using overlay weld method at the outside of pipe, while those in 2 other plants were replaced with new pipes. In this study, the effect of the wall thinning in the main feedwater pipes on piping integrity was evaluated using finite element method. Especially, the effects of both the overlay weld repair and the stress concentration in notch-type thinned area on the piping integrity were investigated. The results are as follows : (1) The piping load carrying capacity may significantly decrease due to FAC. In special, the load carrying capacity of the main feedwater pipe was reduced by about 40% during about 140 months operation in Korean PWR plants. (2) By performing overlay weld repair at the outside of pipe, the piping load carrying capacity can increase and the stress concentration level in the thinned area can be reduced.

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원전 배관의 반복 측정 데이터에 대한 신뢰도 분석 방법 (Reliability Analysis Method for Repeated UT Measurement Data in Nuclear Power Plants)

  • 윤훈;황경모
    • 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.

배관감육 관리를 위한 고정식 및 탈착식 보온재 설치 경제성 분석 (Economic Analysis of Installing Fixed and Removable Insulation for Pipe Wall Thinning Management)

  • 황경모;윤훈
    • Corrosion Science and Technology
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    • 제15권6호
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    • pp.320-325
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    • 2016
  • To perform ultrasonic testing (UT) thickness measurement of the secondary side piping installed in nuclear power plants, the insulation for preventing heat loss should be removed. The type of insulation can be divided into fixed and removable insulation. Fixed and removable insulation have their own strengths and weaknesses. Removable insulation has been installed in the components susceptible to wall thinning caused by FAC and erosion from Shin-Kori unit 1, which commenced its commercial operation in 2011. In this paper, the number of repeated inspections of components and the number of replacements of fixed insulation were estimated and a more economical way was identified based on the manufacturing and installation costs for fixed and removable insulation.

오리피스 유형별 유동가속부식 영향 분석 (Analysis of Flow-Accelerated Corrosion Effects by the Type of Orifice)

  • 황경모;진태은;김경훈
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회B
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    • pp.2483-2488
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    • 2008
  • To mitigate the effects of cavitation and flashing, several types of orifices have been installed in the pipeline of new nuclear power plants. To review the effects of wall thinning caused by flow-accelerated corrosion by the types of orifices, which are cone and plate, and the relation between flow behavior and local wall thinning, experiments and numerical analyses for the downstream pipe of two types of orifices were performed. The experimental results in terms of static pressure obtained for the experimental facilities were compared with those of three-dimensional (3D) numerical analyses using the FLUENT code. As the results of review of flow-accelerated corrosion effects based on the experiment and numerical analysis, it was identified that the orifice of cone-type can be comparatively mitigated the effects of cavitation and flashing, but can not be mitigated the effect of flow-accelerated corrosion.

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Thin-Plate-Type Embedded Ultrasonic Transducer Based on Magnetostriction for the Thickness Monitoring of the Secondary Piping System of a Nuclear Power Plant

  • Heo, Taehoon;Cho, Seung Hyun
    • Nuclear Engineering and Technology
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    • 제48권6호
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    • pp.1404-1411
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    • 2016
  • Pipe wall thinning in the secondary piping system of a nuclear power plant is currently a major problem that typically affects the safety and reliability of the nuclear power plant directly. Regular in-service inspections are carried out to manage the piping system only during the overhaul. Online thickness monitoring is necessary to avoid abrupt breakage due to wall thinning. To this end, a transducer that can withstand a high-temperature environment and should be installed under the insulation layer. We propose a thin plate type of embedded ultrasonic transducer based on magnetostriction. The transducer was designed and fabricated to measure the thickness of a pipe under a high-temperature condition. A number of experimental results confirmed the validity of the present transducer.

실배관 파열실험을 통한 국부감육 곡관 손상압력 평가 (Failure Pressure Evaluation of Local Wall-Thinned Elbows by Real-scale Burst Tests)

  • 김진원;박치용;이성호
    • 대한기계학회논문집A
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    • 제31권10호
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    • pp.1017-1024
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    • 2007
  • This study performed a series of burst tests at ambient temperature using real-scale elbow specimen containing a local wall-thinning defect at it's intrados or extrados and evaluated failure pressure of locally wall-thinned elbows. In the experiment, a 90-degree 100A, Sch. 80 standard elbow was employed, and various wall-thinning geometries, such as length, depth, and circumferential angle, were considered. From the results of experiment, the dependences of failure pressure of wall-thinned elbows on the defect geometries and locations were investigated. In addition, the reliability of existing models was examined by comparing the tests data with the results predicted from existing failure pressure evaluation models for locally wall-thinned elbow.

원전 배관 감육 결함 검사를 위한 IR 열화상시험 조건 결정 (Determination of an Test Condition for IR Thermography to Inspect a Wall-Thinning Defect in Nuclear Piping Components)

  • 김진원;윤경원;정현철;김경석
    • 비파괴검사학회지
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    • 제32권1호
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    • pp.12-19
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    • 2012
  • 본 논문에서는 적외선 열화상 기법을 원전 배관에 적용하여 감육결함을 검사하기 위한 시험 조건을 파악하기 위해서, 인공 결함이 가공된 배관 시편과 평판 시편을 이용하여 적외선 열화상 시험을 수행하였다. 시험에는 할로겐램프를 사용하여 시편을 가열하였으며, 램프의 출력과 시편과 램프의 거리를 변수로 실험을 수행하였다. 시험 결과 시편과 램프의 거리가 1~2 m 이고 램프의 출력이 정격출력의 60 % 이상일 때, 적외선 열화상 기법은 1회 촬영으로 최소한 500 mm 범위 내에 존재하는 원주방향 폭이 $2{\Theta}=90^{\circ}$이고 깊이와 길이가 각각 d/t=0.5와 $L/D_o=0.25$인 배관내 인공 감육 결함들을 검출하였다. 평판 시편과 배관 시편에서 시편과 램프의 거리에 관계없이 램프 출력이 높을수록 결함에 대한 이미지가 선명하였다. 평판 시편과 배관 시편에서 적외선 열화상 방법의 결함 검출 능력은 유사하지만, 최적의 시험 조건은 시편에 따라 다르게 나타났다.

감육배관의 유한요소해석에 의한 변형 및 강도 평가 (Evaluation of Deformation and Strength of Wall Thinne Pipes by Finite Element Analysis)

  • 남기우;안석환;이수식;김진욱;윤자문
    • 한국해양공학회지
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    • 제19권5호
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    • pp.65-70
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    • 2005
  • Fracture behavior and pipe strength are very important to the integrity of energy plants, ocean structures, and so forth. The pipes of energy plants and ocean structures are subject to local wall thinning, resulting from severe erosion-corrosion damage. Recently, the effects of local wall thinning on fracture strength and fracture behavior of piping systems have been the focus of many studies. In this paper, the elasto-plastic analysis is performed by FE code ANSYS on straight pipes with wall thinning. We evaluated the failure mode, fracture strength and fracture behavior, using FE analysis. Also, the effect of the axial strain on deformations and failure modes was estimated by FE analysis.