• Title/Summary/Keyword: stress corrosion crack

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Development the Technique for Fabrication of the Thermal Fatigue Crack to Enhance the Reliability of Structural Component in NPPs (원자력 구조재 신뢰성 향상을 위한 열피로 균열 시험편 제작 기법 개발)

  • Kim, Yong;Kim, Jae-Sung;Lee, Bo-Young
    • Journal of Welding and Joining
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    • v.26 no.2
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    • pp.43-49
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    • 2008
  • Fatigue cracks due to thermal stratification or corrosion in pipelines of nuclear power plants can cause serious problems on reactor cooling system. Therefore, the development of an integrated technology including fabrication of standard specimens and their practical usage is needed to enhance the reliability of nondestructive testing. The test material was austenitic STS 304, which is used as pipelines in the Reactor Coolant System of a nuclear power plants. The best condition for fabrication of thermal fatigue cracks at the notch plate was selected using the thermal stress analysis of ANSYS. The specimen was installed from the tensile tester and underwent continuos tension loads of 51,000N. Then, after the specimen was heated to $450^{\circ}C$ for 1 minute using HF induction heater, it was cooled to $20^{\circ}C$ in 1 minute using a mixture of dry ice and water. The initial crack was generated at 17,000 cycles, 560 hours later (1cycle/2min.) and the depth of the thermal fatigue crack reached about 40% of the thickness of the specimen at 22,000 cycles. As a results of optical microscope and SEM analysis, it is confirmed that fabricated thermal fatigue cracks have the same characteristics as real fatigue cracks in nuclear power plants. The crack shape and size were identified.

Fabrication of Mechanical fatigue flawed Specimen and Evaluation of Flaw Size (기계적 피로결함 시험편 제조 및 결함 크기 평가)

  • Hong, Jae-Keun;Kim, Woo-Sung;Son, Young-Ho;Park, Ban-Uk
    • Journal of the Korean Society for Nondestructive Testing
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    • v.23 no.1
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    • pp.38-44
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    • 2003
  • Performance demonstration with real flawed specimens has been strongly required for nondestructive evaluation of safety class components in nuclear power plant. Mechanical or thermal fatigue crack and intergranular stress corrosion cracking could be occured in the in-service nuclear power plant and mechanical fatigue crack was selected to study in this paper. Specimen was designed to produce mechanical fatigue flaw under tensile stress. The number of cycles and the level of stress were controlled to obtain the desired flaw roughness. After the accurate physical measurement of the flaw size and location, fracture surface was seal-welded in place to ensure the designed location and site. The remaining weld groove was then filled by using gas-tungsten are welding(GTAW) and flux-cored arc welding(FCAW). Results of radio graphic and ultrasonic testing showed that fatigue cracks were consistent with the designed size and location in the final specimens.

Study on the tensile restraint crack characteristics in underwater welds of marine steel plates (선용 강판 수중용접부의 인장 구속 균열 특성에 관한 연구)

  • 오세규;강문호;김민남
    • Journal of Advanced Marine Engineering and Technology
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    • v.11 no.3
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    • pp.45-52
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    • 1987
  • Generally the factors affected largely by the cold cracking sensitivity of the weld are the quantity of the diffusible hydrogen, the brittleness and hardness of the bond area and the tensile restraint stress. These factors have relation each other, and if we can reduce one of these factors, it becomes instrumental to the root cracks prevention of weld. This study deals with the gravity type-underwater-welding of KR Grade A-3 marine steel plate using E4303 welding electrode in order to compare wet-underwater-welding with in-air- welding, resulting in obtaining the tensile restraint characteristics, the hardness distribution, the quantity of diffusible hydrogen and the macro- and micro-crack properties in both underwater and in-air welds. The main results obtained are as follows: 1) The quantity of diffusible hydrogen measured for 48 hours is about 18cc/100g-weld-metal for the in-air-weld of one pass and about 48cc/100g-weld-metal for the underwater-weld of one pass which is about 3 times penetration of diffusible hydrogen compairing with the case of the in-air-weld. However, it was experimentally confirmed that, by the multi-pass welding of 2 to 5 passes, the diffusible hydrogen in the underwater weld metal can be reduced as much as 27 to 49%. 2) The hardness of the weld metal indicates the highest value in the heat affected zones of underwater weld for more rapid cooling rate, resulting in the higher sensitivity of cold cracking. So, it is desirable to soften the higher hardness in the HAZ by tempering effect such as the multi-pass welding in the underwater welding. 3) At the bond vicinity of the underwater weld HAZ, micro cracks were found as resulted by both more rapid cooling rate and more diffusible hydrogen and also by the stress corrosion cracking under the tensile restraint stress in the underwater. But this could be prevented by the tempering effect of the following weld bead such as the multi-pass welding.

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Grain Boundary Character Changes and IGA/PWSCC Behavior of Alloy 600 Material by Thermomechanical Treatment (가공열처리에 의한 Alloy 600 재료의 결정립계특성 변화와 입계부식 및 1차측 응력부식균열 거동)

  • Kim, J.;Han, J.H.;Lee, D.H.;Kim, Y.S.;Roh, H.S.;Kim, G.H.;Kim, J.S.
    • Korean Journal of Materials Research
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    • v.9 no.9
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    • pp.919-925
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    • 1999
  • Grain boundary characteristics and corrosion behavior of Alloy 600 material were investigated using the concept of grain boundary control by thermomechanical treatment(TMT). The grain boundary character distribution (GBCD) was analyzed by electron backscattered diffraction pattern. The effects of GBeD variation on intergranular at tack(JGA) and primary water stress corrosion cracking(PWSeC) were also evaluated. Changes in the fraction of coinci dence site lattice(CSL) boundaries in each cycle of TMT process were not distinguishable, but the total eSL boundary frequencies for TMT specimens increased about 10% compared with those of the commercial Alloy 600 material. It was found from IGA tests that the resistance to IGA was improved by TMT process. However, it was found from PWSCC test that repeating of TMT cycles resulted in the gradual decrease of the time to failure and the maximum load due to change in grain boundary characteristics, while the average crack propagation rate of primary crack increased mainly due to suppression of secondary crack propagation. It is considered that these corrosion characteristics in TMT specimens is attributed to 'fine tuning of grain boundary' mechanism.

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Strain Distribution Measurement for Wall Thinning Defect in Pipe Bends by ESPI (ESPI 를 이용한 곡관 감육 결함부의 변형률 분포 측정)

  • Naseem, Akhter;Kim, Koung-Suk;Jung, Sung-Wook;Park, Jong-Hyun;Choi, Jung-Suk;Jung, Hyun-Chul
    • Proceedings of the KSME Conference
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    • 2007.05a
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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.

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An Evaluation of Failure Behavior of Pipe with Local Wall Thinning by Pipe Experiment (배관실험을 통한 국부감육 배관의 손상거동 평가)

  • Kim, Jin-Won;Park, Chi-Yong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.26 no.4
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    • pp.731-738
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    • 2002
  • To understand failure behavior of pipe thinned by flow accelerated corrosion, in this study, the pipe failure tests were performed on 102mm-Sch.80 carbon steel pipe with various local wall thinning shapes, and the failure mode, load carrying capacity, and deformability were investigated. The tests were conducted under loading conditions of 4-points bending and internal pressure. The experimental results showed that the failure mode of thinned pipe depended on magnitude of internal pressure and thinning length as well as loading direction and thinning depth and angle. The variation in load carrying capacity and deformability of thinned pipe with thinning length was determined by stress type appled to the thinning area and circumferential thinning angle. Also, the effect of internal pressure on failure behavior was dependent on failure mode of thinned pipe, and it promoted crack occurrence and mitigated local buckling at thinned area.

Effects on Machining on Surface Residual Stress of SA 508 and Austenitic Stainless Steel (SA508 탄소강 및 오스테나이트 스테인리스강의 표면잔류응력에 미치는 기계가공효과)

  • Lee, Kyoung-Soo;Lee, Seong-Ho;Park, Chi-Yong;Yang, Jun-Seok;Lee, Jeong-Geun;Park, Jai-Hak
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.35 no.5
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    • pp.543-547
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    • 2011
  • Primary water stress corrosion cracking has occurred in dissimilar weld areas in nuclear power plants. Residual stress is a driving force in the crack. Residual stress may be generated by weld or surface machining. Residual stress due to surface machining depends on the machining method, e.g., milling, grinding, or EDM. The stress is usually distributed on or near the surface of the material. We present the measured residual stress for machining on SA 508 and austenitic stainless steels such as TP304 and F316. The residual stress can be tensile or compressive depending on the machining method. The depth and the magnitude of the residual stress depend on the material and the machining method.

Effect of wall Thinning on the Failure of Pipes Subjected to Bending Load (굽힘하중을 받는 배관의 파손에 미치는 감육의 영향)

  • AHN SEOK-HWAN;LEE SOO-SIG;NAM KI-WOO
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2004.11a
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    • pp.242-246
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    • 2004
  • Effects of circumferentially local wall thinning on the fracture behavior of pipes were investigated by monotonic four-point bending. Local wall thinning was machined on the pipes in order to simulate erosion/corrosion metal loss. The configurations of the eroded area included an eroded ratio of d/t= 0.2, 0.5, 0.6, and 0.8, and an eroded length of I = 10 mm, 25 mm, and 120 mm. Fracture type could be classified into ovalization, local buckling, and crack initiation depending on the eroded length and eroded ratio. Three-dimensional elasto-plastic analyses were also carried out using the finite element method, which is able to accurately simulate fracture behaviors excepting failure due to cracking. It was possible to predict the crack initiation point by estimating true fracture ductility under multi-axial stress conditions at the center of the eroded area.

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Strength Properties and Elastic Waves Characteristics of Silicon Carbide with Damage-Healing Ability (손상치유 능력을 가지는 탄화규소의 강도 특성과 탄성파 특성)

  • KIM MI-KYUNG;AHN BYUNG-GUN;KIM JIN-WOOK;PARK IN-DUCK;AHN SEOK-HWAN;NAM KI-Woo
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2004.05a
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    • pp.337-341
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    • 2004
  • Engineering ceramics have superior heat resistance, corrosion resistance, and wear resistance. Consequently, these art significant candidates for hot-section structural components of heat engine and the inner containment of nuclear fusion reactor. Besides, some of them have the ability to heal cracks and great benefit can be anticipated with great benefit the structural engineering field. Especially, law fracture toughness of ceramics supplement with self-healing ability. In the present study, we have been noticed some practically important points for the healing behavior of silicon nitride, alumina, mullite with SiC particle and whisker. The presence of silicon carbide (SiC) in ceramic compound is very important for crack-healing behavior. However, self-healing of SiC has not been investigated well in detail yet. In this study, commercial SiC was selected as sample, which can be anticipated in the excellent crack healing ability. The specimens were produced three-point bending specimen with a critical semi-circular crack of which size that is about $50-700{\mu}m$. Three-point bending test and static fatigue test were performed cracked and healed SiC specimens. A monotonic bending load was applied to cracked specimens by three-point loading at different temperature. The purpose of this paper is to report Strength Properties and Elastic Waves Characteristics of Silicon Carbide with Crack Healing Ability.

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Effect of Normal Operating Condition Analysis Method for Weld Residual Stress of CRDM Nozzle in Reactor Pressure Vessel (원전 정상가동조건 적용 방식이 원자로 압력용기 상부헤드 관통 노즐의 용접 잔류응력에 미치는 영향)

  • Nam, Hyun Suk;Bae, Hong Yeol;Oh, Chang Young;Kim, Ji Soo;Kim, Yun Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.9
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    • pp.1159-1168
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    • 2013
  • In pressurized water nuclear reactors (PWRs), the reactor pressure vessel (RPV) upper head contains penetration nozzles that use a control rod drive mechanism (CRDM). The penetration nozzle uses J-groove weld geometry. Recently, the occurrence of cracking in alloy 600 CRDM penetration nozzle has increased. This is attributable to primary water stress corrosion cracking (PWSCC). PWSCC is known to be susceptible to the welding residual stress and operational stress. Generally, the tensile residual stress is the main factor contributing to crack growth. Therefore, this study investigates the effect on weld residual stress through different analysis methods for normal operating conditions using finite element analysis. In addition, this study also considers the effect of repeated normal operating condition cycles on the weld residual stress. Based on the analysis result, this paper presents a normal operating condition analysis method.