• Title/Summary/Keyword: Corrosion Integrity Evaluation

Search Result 72, Processing Time 0.02 seconds

Characteristic Evaluation according to Heat Treatment Conditions of Super Duplex Stainless Steel with Additive 0.2% N - Part 2: Fatigue Crack Propagation Behavior (0.2% N을 첨가한 수퍼 2상 스테인리스강의 열처리 조건에 따른 특성 평가 - 제2보: 피로균열진전 거동)

  • Ahn, Seok-Hwan;Kang, Heung-Joo;Seo, Hyun-Soo;Nam, Ki-Woo;Lee, Kun-Chan
    • Journal of Ocean Engineering and Technology
    • /
    • v.23 no.5
    • /
    • pp.79-84
    • /
    • 2009
  • Super duplex stainless steel has long life in severe environments by showing the enough strength and corrosion resistance. Therefore, the fracture mechanics approach needs to support the structural strength integrity for the used material. In this study, fatigue crack propagation behavior was investigated to super duplex stainless steel with 0.2% nitrogen. The various volume fraction and distribution of austenite structure for applied specimen in test were obtained by changing the heat treatment temperature and cycle. From test results, fatigue crack propagation rate showed two kinds of tendency between da/dN and ${\Delta}K$ according to distribution of austenite structure and structure anisotropy.

A Study on the Integrity Evaluation Method of Subclad Crack under Pressurized Thermal Shock (가압열충격 사고시 클래스 하부균열 안전성 평가 방법에 관한 연구)

  • Koo, Bon-Geol;Kim, Jin-Su;Choi, Jae-Boong;Kim, Young-Jin
    • Proceedings of the KSME Conference
    • /
    • 2000.11a
    • /
    • pp.286-291
    • /
    • 2000
  • The reactor pressure vessel is usually cladded with stainless steel to prevent corrosion and radiation embrittlement, and number of subclad cracks have been found during an in-service-inspection. Therefore assessment for subclad cracks should be made for normal operating conditions and faulted conditions such as PTS. Thus, in order to find the optimum fracture assessment procedures for subclad cracks under a pressurized thermal shock condition, in this paper, three different analyses were performed, ASME Sec. XI code analysis, an LEFM(Liner elastic fracture mechanics) analysis and an EPFM(Elastic plastic fracture mechanics) analysis. The stress intensity factor and the Maximum $RT_{NDT}$ were used for characterizing. Analysis based on ASME Sec. XI code does not completely consider the actual stress distribution of the crack surface, so the resulting Maximum allowable $RT_{NDTS}$ can be non-conservative, especially for deep cracks. LEFM analysis, which does not consider elastic-plastic behavior of the clad material, is much more non-conservative than EPFM analysis. Therefore, It is necessary to perform EPFM analysis for the assessment of subclad cracks under PTS.

  • PDF

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

  • NAM KI-WOO;AHN SEOK-HWAN;LEE SOO-SIG;KIM JIN-WOOK;YOON JA-MUN
    • Journal of Ocean Engineering and Technology
    • /
    • v.19 no.5 s.66
    • /
    • pp.65-70
    • /
    • 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.

Quantitative EC Signal Analysis on the Axial Notch Cracks of the SG Tubes (SG Tube 축방향 노치 균열의 정량적 EC 신호평가)

  • Min, Kyong-Mahn;Park, Jung-Am;Shin, Ki-Seok;Kim, In-Chul
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.29 no.4
    • /
    • pp.374-382
    • /
    • 2009
  • Steam generator(SG) tube, as a barrier isolating primary to the secondary coolant system of nuclear power plants(NPP), must maintain the structural integrity far the public safety and its efficient power generation capacity. And SG tubes bearing defects must be timely detected and taken repair measures if needed. For the accomplishment of these objectives, SG tubes have been periodically examined by eddy current testing(ECT) on the basis of administrative notices and intensified SG management program(SGMP). Stress corrosion cracking(SCC) on the SG tubes is not easily detected and even missed since it has lower signal amplitude and other disturbing factors against its detection. However once SCC is developed, that can cause detrimental affects to the SG tubes due to its rapid propagation rate. Accordingly SCC is categorized as prime damage mechanism challenging the soundness of the SG tubes. In this study, reproduced EDM notch specimens are examined for the detectability and quantitative characterization of the axial ODSCC by +PT MRPC probe, containing pancake, +PT and shielded pancake coils apart in a single plane around the circumference. The results of this study are assumed to be applicable fur providing key information of engineering evaluation of SCC and improvement of confidence level of ECT on SG tubes.

Application of a New NDI Method using Magneto-Optical Film for Inspection of Micro-Cracks (미소균열 탐상을 위한 자기광학소자를 이용한 비파괴탐상법의 제안과 적용)

  • Lee, Hyoung-No;Park, Han-Ju;Shoji, Tetsuo
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.21 no.2
    • /
    • pp.197-203
    • /
    • 2001
  • Micro-defects induced by design and production failure or working environments are known as the cause of SCC(Stress Corrosion Cracking) in aged structures. Therefore, the evaluation of structural integrity based on micro-cracks is required not only a manufacturing step but also in-service term. So we introduce a new nondestructive inspection method using the magneto-optical film to detect micro-cracks. The method has some advantage such as high testing speed, real time data acquistion and the possibility of remote sensing by using of a magneto-optical film that takes advantage of the change of magnetic domains and domain walls. This paper introduces the concept of the new nondestructive inspection method using the magneto-optical film, also proves the possibility of this method as a remote testing system under oscillating load considering application on real fields by applying the method to four types of specimens.

  • PDF

A Study on the Profile Change Measurement of Steam Generator Tubes with Tube Expansion Methods

  • Kim, Young-Kyu;Song, Myung-Ho;Choi, Myung-Sik
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.31 no.5
    • /
    • pp.543-551
    • /
    • 2011
  • Steam generator tubes for nuclear power plants contain the local shape transitions on their inner or outer surface such as dent, bulge, over-expansion, eccentricity, deflection, and so on by the application of physical force during the tube manufacturing and steam generator assembling and by the sludge (that is, corrosion products) produced during the plant operation. The structural integrity of tubes will be degraded by generating the corrosive crack at that location. The profilometry using the traditional bobbin probes which are currently applied for measuring the profile change of tubes gives us basic information such as axial locations and average magnitudes of deformations. However, the three-dimensional quantitative evaluation on circumferential locations, distributional angle, and size of deformations will have to be conducted to understand the effects of residual stresses increased by local deformations on corrosive cracking of tubes. Steam generator tubes of Korean standard nuclear power plants expanded within their tube-sheets by the explosive expansion method and suffered from corrosive cracks in the early stage of power operation. Thus, local deformations of steam generator tubes at the top of tube-sheet were measured with an advanced rotating probe and a laser profiling system for the two cases where the tubes expanded by the explosive expansion method and hydraulic expansion. Also, the trends of eccentricity, deflection, and over-expansion of tubes were evaluated. The advanced eddy current profilometry was confirmed to provide accurate information of local deformations compared with laser profilometry.

A Study for Experiment to Measure Mechanical Properties of Pressurizer Nozzle and Safety-Ends in Nuclear Power Plant (원전 가압기 노즐 및 안전단 재료에 대한 기계적 물성시험 연구)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Kim, Jin-Weon
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.33 no.2
    • /
    • pp.147-153
    • /
    • 2013
  • Recently the primary water stress corrosion cracking(PWSCC) has occurred in the dissimilar metal weld region between pressurizer nozzle and safe-end in nuclear power plants(NPPs). As material of the pressurizer nozzle, SA508 Gr. 3 low alloy steel was used. F316L stainless steel and Alloy 82/182 were used as safe-end and weld metal, respectively. Although mechanical properties are needed for evaluation of the structural integrity against flaw in the material, material specification and standard don't supply those properties. Therefore, the present study conducted tensile and fracture toughness tests on SA508 Gr.3 and F316L stainless steel at ambient temperature and operating temperature of NPPs and reported the tested results.

Study on Plugging Criteria for Thru-wall Axial Crack in Roll Transition Zone of Steam Generator Tube (증기발생기 전열관 확관천이부위 축방향 관통균열의 관막음 기준에 관한 연구)

  • Park, Myeong-Gyu;Kim, Yeong-Jong;Jeon, Jang-Hwan;Kim, Jong-Min;Park, Jun-Su
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.20 no.9
    • /
    • pp.2894-2900
    • /
    • 1996
  • The stream generator tubes represent an integral part of a major barrier against the fission product release to the environment. So, the rupture of these tubes could permit flow of reactor coolant into the secondary system and injure the safety of reactor coolant system. Therefore, if the crack was detected during In-Service Inspection of tubes the cracked tube should be evaluated by the pulgging criteria and plugged or not. In this study, the fracture mechanics evaluation is carried out on the thru-wall axial crack due to Primary Water Stress Corrosion Cracking in the roll transition aone of steam generator tube to help the assurence the integrity of tubes and estabilish the plugging criteria. Due to the Inconel which is used as tube material is more ductile than others, the plastic instability repture theory was used to calculate the critical and allowable crack length. Based on Leak Before Break concept the leak rate for the critical crack length and the allowable leak rate are compared and the safety of tubes was given.

AE Characteristic of Polyethylene Pipe under various defects (다양한 결함에 대한 폴리에틸렌 배관의 음향방출 특성)

  • Nam Ki Woo;Lee Si Yoon;Ahn Seok Hwan
    • Journal of the Korean Institute of Gas
    • /
    • v.8 no.3 s.24
    • /
    • pp.1-7
    • /
    • 2004
  • The polyethylene pipe can use semi-permanent because of the high corrosion resistance with chemical stability. In addition to, there is the merit that is an easy to establish and to maintain. However, as the reason that it is simply degraded when the polyethylene pipe was exposed to the outside, mainly it is used to lay under the ground with low-pressure gas transportation pipe. In this study, the nondestructive evaluation method was used to maintain the integrity of the polyethylene pipe. We simulated the various defects on the polyethylene pipes, and then the AE signal occurred according to the impact test of steel ball was evaluated by the acoustic emission method. From the results, the waveform and dominant frequency could be distinguishing from the defect shapes of polyethylene pipe. Especially, in the case of notch defect, the AE signals occur different by the angle and depth of the notch.

  • PDF

Feasibility Study on the Utilization of EMAT Technology for In-line Inspection of Gas Pipeline

  • Cho, Sung-Ho;Yoo, Hui-Ryong;Rho, Yong-Woo;Kim, Hak-Joon;Kim, Dae-Kwang;Song, Sung-Jin;Park, Gwan-Soo
    • Journal of Magnetics
    • /
    • v.16 no.1
    • /
    • pp.36-41
    • /
    • 2011
  • If gas is leaking out of gas pipelines, it could cause a huge explosion. Accordingly, it is important to ensure the integrity of gas pipelines. Traditionally, over the years, gas-operating companies have used the ILI system, which is based on axial magnetic flux leakage (MFL), to inspect the gas pipelines. Relatively, there is a low probability of detection (POD) for the axial defects with the axial MFL-based ILI. To prevent the buried pipeline from corrosion, it requires a protective coating. In addition to the potential damage to the coating by environmental factors and external forces, there could be defects on the damaged coating area. Thus, it is essential that nondestructive evaluation methods for detecting axial defects (axial cracks, axial groove) and damaged coating be developed. In this study, an electromagnetic acoustic transducer (EMAT) sensor was designed and fabricated for detecting axial defects and coating disbondment. In order to validate the performances of the developed EMAT sensor, experiments were performed with specimens from axial cracks, axial grooves, and coating disbondment. The experimental results showed that the developed EMAT sensor could detect not only the axial cracks (minimum 5% depth of wall thickness) and axial grooves (minimum 10% depth of wall thickness), but also the coating disbondment.