• Title/Summary/Keyword: Wall thinning pipe

Search Result 141, Processing Time 0.021 seconds

Introduction and Feasibility on a New Technology for the Pipe Wall Thinning Evaluation of Nuclear Power Plants (원전 배관감육 평가를 위한 새로운 기법의 도입 및 타당성)

  • Hwang, Kyeong Mo;Yun, Hun;Park, Hyun Cheol
    • Corrosion Science and Technology
    • /
    • v.13 no.2
    • /
    • pp.62-69
    • /
    • 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.

Cause Analysis for the Wall Thinning and Leakage of a Small Bore Piping Downstream of an Orifice (주증기계통 오리피스 후단 소구경 배관의 감육 및 누설 발생)

  • Hwang, Kyeong Mo
    • Corrosion Science and Technology
    • /
    • v.12 no.5
    • /
    • pp.227-232
    • /
    • 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.

A study on forming analysis for the soft pipe bending process of thickness guarantee (연질파이프의 두께보증형 벤딩공정에 대한 성형해석에 대한 연구)

  • Jung, Dong-Won;Jeong, Ji-Hyun;Cho, Jong-Rae
    • Journal of Advanced Marine Engineering and Technology
    • /
    • v.37 no.1
    • /
    • pp.66-71
    • /
    • 2013
  • Soft bending pipe is widely used for freezing equipment and shipbuilding. These pipe have some problems that they cause occasionally outside wrinkle, crack, wall thinning phenomena. However, vending machines which have been made to solve the problems completely, are not yet. In this study, to settle these problems, we proved the effectiveness of the self-made mandrel by results of simulation as the basic for the development of precision high-quality vending machine ; presents the solution method of the wall thinning phenomena by analyzing circular deformation and damage of bending pipe.

Development and demonstration of an erosion-corrosion damage simulation apparatus (배관 침부식 손상 연속모사 장비 개발 및 실증)

  • Nam, Won Chang;Ryu, Kyung Ha;Kim, Jae Hyoung
    • Corrosion Science and Technology
    • /
    • v.12 no.4
    • /
    • pp.179-184
    • /
    • 2013
  • Pipe wall thinning caused by erosion and corrosion can adversely affect the operation of aged nuclear power plants. Some injured workers owing to pipe rupture has been reported and power reduction caused by unexpected pipe damage has been occurred consistently. Therefore, it is important to develop erosion-corrosion damage prediction model and investigate its mechanisms. Especially, liquid droplet impingement erosion(LDIE) is regarded as the main issue of pipe wall thinning management. To investigate LDIE mechanism with corrosion environment, we developed erosion-corrosion damage simulation apparatus and its capability has been verified through the preliminary damage experiment of 6061-Al alloy. The apparatus design has been based on ASTM standard test method, G73-10, that use high-speed rotator and enable to simulate water hammering and droplet impingement. The preliminary test results showed mass loss of 3.2% in conditions of peripheral speed of 110m/s, droplet size of 1mm-diameter, and accumulated time of 3 hours. In this study, the apparatus design revealed feasibility of LDIE damage simulation and provided possibility of accelerated erosion-corrosion damage test by controlling water chemistry.

Dual Core Differential Pulsed Eddy Current Probe to Detect the Wall Thickness Variation in an Insulated Stainless Steel Pipe

  • Angani, C.S.;Park, D.G.;Kim, C.G.;Kollu, P.;Cheong, Y.M.
    • Journal of Magnetics
    • /
    • v.15 no.4
    • /
    • pp.204-208
    • /
    • 2010
  • Local wall thinning in pipelines affects the structural integrity of industries like nuclear power plants (NPPs). In the present study, a pulsed eddy current (PEC) differential probe with two excitation coils and two Hall-sensors was fabricated to measure the wall thinning in insulated pipelines. A stainless steel test sample was prepared with a thickness that varied from 1 mm to 5 mm and was laminated by plastic insulation to simulate the pipelines in NPPs. The excitation coils in the probe were driven by a rectangular current pulse, the difference of signals from two Hall-sensors was measured as the resultant PEC signal. The peak value of the detected signal is used to describe the wall thinning. The peak value increased as the thickness of the test sample increased. The results were measured at different insulation thicknesses on the sample. Results show that the differential PEC probe has the potential to detect wall thinning in an insulated NPP pipelines.

Stress Evaluation and Case Study of Reinforced Wall-thinned Class 2 and 3 Pipes in Operating Nuclear Power Plants Using Equivalent Stiffness Concept (등가 강성 개념을 이용한 가동 원전 2, 3등급 감육 보강 배관의 응력 평가 및 사례해석)

  • Xinyu Ma;Jae Yoon Kim;Jin Ha Hwang;Yun Jae Kim;Man Won Kim
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.18 no.2
    • /
    • pp.54-60
    • /
    • 2022
  • ASME BPVC provides stress evaluation rules for Class 2 and 3 nuclear piping. However, such rules are difficult to be applied to reinforced wall-thinned pipes during service. To resolve this issue, a new method for stress evaluation of reinforced wall-thinned pipes is proposed in this work, based on the equivalent stiffness concept. By converting a reinforced wall-thinned pipe to an equivalent straight pipe having the same stiffness, stress evaluation can be proceeded using the current ASME BPVC rules. The proposed method is applied to pipes with 4 different normal pipe size and the effects of reinforcement and wall-thinning dimensions on evaluated stresses are discussed.

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

  • Yun, Hun;Hwang, Kyeong-Mo
    • Corrosion Science and Technology
    • /
    • v.12 no.3
    • /
    • pp.142-148
    • /
    • 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.

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

  • Hwang, Kyeongmo;Yun, Hun
    • Corrosion Science and Technology
    • /
    • v.15 no.6
    • /
    • pp.320-325
    • /
    • 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.