• Title/Summary/Keyword: 부식균열

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Experimental Study on Artificial Crack Healing for Concrete Using Electrochemical Deposition Method (전기화학적 전착기법을 활용한 콘크리트의 인공 균열치유에 관한 실험적 연구)

  • Lee, Chang-Hong;Song, Ha-Won
    • Journal of the Korea Concrete Institute
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    • v.21 no.4
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    • pp.409-417
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    • 2009
  • In this study, autogenous crack healing and artificial crack healing using electrochemical electro deposition method were conducted to compare in the aspects of corrosion monitoring. Furthermore, the analysis of impressed voltage characteristics, galvanic current and linear polarization resistance comparison, and photo image processing technique were performed for quantitative comparisons of healing ratio. As a result, it was found that, in view of impressed voltage of artificial crack healing, the measured voltage was increased as time goes by. From the galvanic test results of artificial crack healing, the current vs. potential distribution value were formed widely in comparison with autogenous crack healing. In this point, it was shown that artificial crack healing has more eleatic resistance capacity than autogenous crack healing technique. Finally, it was found that artificial crack healing was 1.63 times higher than autogenous healing in view of crack healing ratio.

Evaluation of Eddy Current Signals from the Inner Wall Axial Cracks of Steam Generator Tubes (증기발생기 전열관의 내면 축방향 균열에 대한 ECT 특성 평가)

  • Choi, Myung-Sik;Hur, Do-Haeng;Lee, Doek-Hyun;Park, Jung-Am;Han, Jung-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.21 no.5
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    • pp.501-509
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    • 2001
  • For the enhancement of ECT reliability on the primary water stress corrosion cracks of nuclear steam generator tubes, of which the occurrence is on the increase, it is important to comprehend the signal characteristics on crack morphology and to select an appropriate probe type. In this paper, the sizing accuracy and the detectability for the inner wall axial cracks of tubes were quantitatively evaluated using the following specimens: the electric discharge machined notches and the corrosion cracks which were developed on the operating steam generator tubes. The difference of eddy current signal characteristics between pancake and axial coil were also Investigated. The results obtained from this study provide a useful information for more precise evaluation on the inner wall axial tracks oi stram generator tubes.

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An Effect of Steel Corrosion on Bond Stress-slip Relationship under Repeated Loading (반복하중하의 부착응력-슬립 관계에 미치는 철근 부식의 영향)

  • Kim, Chul-Min;Park, Jong-Bum;Chang, Sung-Pil;Kim, Jee-Sang
    • Journal of the Korea Concrete Institute
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    • v.22 no.2
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    • pp.179-186
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    • 2010
  • The bond between steel and concrete in reinforced concrete members is essential to resist external load, but the bond mechanism in reinforced concrete beams deteriorated by steel corrosion has not been clearly known yet. Most existing researches have dealt with the bond behavior of corroded steel under monotonic loading, but scarce are researches dealing with bond behavior of corroded steel under repeated loading. This study includes the experimental investigation on the bond behavior with respect to the various degrees of steel corrosion under repeated loading. According to the test results, the bond strength of corroded steel under monotonic loading increases as the rate of steel corrosion increases unless the splitting crack occurs. The slip versus number of load cycles relation was found to be approximately linear in double logarithmic scale, not only in specimens without steel corrosion but also in specimens with steel corrosion. The test results also show that the steel corrosion does not negatively affect the bond strength of corroded steel after repeated loading unless the splitting crack occurs. But the fatigue life decreases sharply after splitting crack occurs. This research will be helpful for the realistic durability design and condition assessment of reinforced concrete structures.

Sensitivity Analysis of Nozzle Geometry Variables for Estimating Residual Stress in RPV CRDM Penetration Nozzle (원자로 상부헤드 관통노즐의 잔류응력 예측을 위한 노즐 형상 변수 민감도 연구)

  • Bae, Hong Yeol;Oh, Chang Young;Kim, Yun Jae;Kim, Kwon Hee;Chae, Soo Won;Kim, Ju Hee
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.3
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    • pp.387-395
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    • 2013
  • Recently, several circumferential cracks were found in the control rod drive mechanism (CRDM) nozzles of U.S. nuclear power plants. According to the accident analyses, coolant leaks were caused by primary water stress corrosion cracking (PWSCC). The tensile residual stresses caused by welding, corrosion sensitive materials, and boric acid solution cause PWSCC. Therefore, an exact estimation of the residual stress is important for reliable operation. In this study, finite element simulations were conducted to investigate the effects of the tube geometry (thickness and radius) on the residual stresses in a J-groove weld for different CRDM tube locations. Two different tube locations were considered (center-hole and steepest side hill tube), and the tube radius and thickness variables ($r_o/t$=2, 3, 4) included two different reference values ($r_o$=51.6, t=16.9mm).

Development of New Code Case "Mitigation of PWSCC and CISCC in ASME Code Section III Components by the Advanced Surface Stress Improvement Technology (일차수응력부식균열(PWSCC) 및 염화이온부식균열(CISCC) 저감용 표면개질기술 적용을 위한 코드케이스 개발)

  • Cho, Sungwoo;Pyun, Youngsik;Mohr, Nick;Tatman, Jon;Broussard, John;Collin, Jean;Yi, Wongeun;Oh, Eunjong;Jang, Donghyun;Koo, Gyeong Hoi;Hwang, Seong Sik;Choi, Sun Woong;Hong, Hyun UK
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.15 no.1
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    • pp.28-32
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    • 2019
  • In nuclear power plant operation and spent fuel canisters, it is necessary to provide a sound technical basis for the safety and security of long-term operation and storage respectively. Recently, the peening technology is being discussed and the technology will be adopted to ASME Section III, Division 1, Subsection NX (2019 Edition). The peening is prohibited in current edition, but it will be approved in 2019 Edition and adopted. However, Surface stress improvement techniques such as the peening is used to mitigate SCC susceptible in operating nuclear plants. Although the peening will be approved to ASME CODE, there are no performance criteria listed in the 2019 edition. The Korean International Working Group (KIWG) formed a new Task Group named "Advanced Surface Stress Improved Technology". The task group will develop a CODE CASE to address PWSCC(Primary Water Stress Corrosion Cracking) and CISCC(Chloride Induced Stress Corrosion Cracking) for new ASME Section III components. TG-ASSIT was started to make peening performance criteria for ASME Section III (new fabrication) applications. The objective of TG-ASSIT is to gain consensus among the relevant Code groups that requirements/mitigation have been met.

부식환경에서의 파괴 및 피로

  • 이동영
    • Journal of the KSME
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    • v.28 no.4
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    • pp.313-321
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    • 1988
  • 어떤 구조물이 반복하중을 받으면 피로파괴를 일으킨다. 만일 이 구조물이 부식환경 속에 앗 으면 불활성 분위기나 공기 중에서 보다 빨리 파괴에 이르게 된다. 이러한 현상을 흔히 부식 피로라고 한다. 부식피로에 크게 영향을 미치는 변수들을 대략 기계적 변수, 금속학적 변수, 환경 변수로서, 기계적 변수에는 최대응력 확대계수, 응력확대계수범위, 응력비, 반복하중 주파수, 반복하중파형, 응력상태, 잔류응력, 균열의 크기 및 모양 등이 있으며 금속학적 변수로는 합금 조성, 합금원소와 불순물의 분포, 미세조직과 결정구조, 열처리, 소성가공, 집합조직 등이며 환 경변수에는 온도, 환경의 형태(기체, 액체), 부식성분의 분압 또는 농도, 전기화학적 전위, pH, 수용성 환경의 점성, 피복, 부식억제제 등이 있다. 이와 같이 부식환경 속에 있는 구조물의 파 손을 이해하기 위하여는 응력부식과 부식피로를 공부하여야 한다. 이 현상은 매우 복잡한 문 제이기 때문에 아직도 완전히 이해되지 않은 상태이고 따라서 중요한 연구대상이 되고 있다. 여기서는 응력부식과 부식피로의 파괴역학적인 측면을 소개하고자 한다.

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A study on the characteristics of corrosion-fatigue-crack propagation in the welded parts of high tensile steels under sea water (고장력강 용접부의 해수중 부식피로균열 성장특성에 관한 연구)

  • 김영식;박무창
    • Journal of Ocean Engineering and Technology
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    • v.1 no.2
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    • pp.113-122
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    • 1987
  • Ships and offshore strrctures are exposed to the corrosive surroundings, and the extablishment of the design criteria and the elucidation on the influence by this environment are requested to maintain the safety and to demonstrate the function of the structure. In this paper, the fatigue-crack-growth behavior on the compact tension specimens of quenched, tempered HT80 grade steels and RA36 high tensile steels having a single edge fatigue cracked notch respectively, were investigated under the repeated tensile stress with constant stroke in sea water for the welded parts by shielded metal arc welding. Main results obtained are summerized as follows; 1. The fatigue-crack-growth rates da/dN in sea water appeared to be greater behavior than those in air environment at the same stress intensisy factor range $\DeltaK$. 2. The correlation data of da/dN$\DeltaK$ of the two kinds of high tensile steels in sea water showed no great difference, however, the correlation data of da/dN$\DeltaK/\sigma_y$($\sigma_y$ stands for yield strength of the material) showed that the fatigue-crack-growth behavior of RA36 plate is affected by active path corrosion(APC) mechanism, while that of HT80 grade plate is mainly affected by hydrogen embrittlement mechanism.

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고온의 염기성 수용액에서 Ni기 합금의 응력부식파괴

  • 김홍표;황성식;국일현;김정수
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.84-89
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    • 1998
  • Alloy 600 및 alloy 690과 Ni-8Cr-lOFe 합금 등의 응력부식(stress corrosion cracking, SCC) 거동을 고온의 염기성 분위기에서 C-ring 시편을 사용하여 연구하였다. Alloy 600과 alloy 690을 여러 조건에서 열처리하여 etching한 후 탄화물의 분포와 입계 주변의 Cr고갈 정도 등의 미세조직을 광학현미경과 주사 전자현미경(SEM)으로 관찰하였다. 이들 재료에 대한 SCC 시험을 315$^{\circ}C$의 40% NaOH 수용액에서 일정한 부하전위(부식전위 + 200㎷)를 가하면서 수행하였으며, 동일 조건에서의 분극거동도 측정하였다. Alloy 600 MA(mill anneal) 및 TT(thermal treatment)의 SCC 저항성은 alloy 690 TT와 Ni-8Cr-10Fe SA(solution anneal)보다 낮았다. Alloy 600 TT 재료는 alloy 600 MA 및 SA 재료에 비해 SCC 저항성이 더 컸다. 고용 탄소농도는 alloy 600의 SCC 저항성에 큰 영향을 주지 못했다. 대부분의 Alloy 600은 균열전파 입계균열을 보였으나, 일부에서는 입계 및 입내 혼합양상(mixed mode cracking)을 보였다. 염기성 분위기에서 Ni기 합금의 SCC 거동을 미세조직, 분극거동의 관점에서 고찰하였다.

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Prediction of Cover Concrete Cracking due to Chloride Induced Corrosion in Concrete Structures (콘크리트 구조물의 염해부식에 따른 덮개콘크리트의 균열예측)

  • Lim, Dong-Woo;Lee, Chang-Hong;Song, Ha-Won
    • Proceedings of the Korea Concrete Institute Conference
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    • 2009.05a
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    • pp.291-292
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    • 2009
  • In this study, an analysis of cover concrete cracking exposed to the chloride attack was performed based on newly defined durability limit states. Using the methodology in this paper, the prediction of cover concrete cracking and subsequent spalling can be used for the prediction of corrosion induced serviceability degradation of concrete structures subjected chloride attack.

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Susceptibility of Stress Corrosion Crack Initiation of Type 304 SS in Simulated Primary Water Environment of PWR (원전 1차 계통수 모사환경에서 Type 304 스테인리스강의 응력부식균열개시 민감도)

  • Sung-Hwan Cho;Sung-Woo Kim;Jong-Yeon Lee
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.20 no.1
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    • pp.25-31
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    • 2024
  • The core shroud of rector vessel internals (RVI) of OPR1000 and ARP1400 is made of Type 304 stainless steel (SS) by bending and welding process that may induce high deformation and residual stress in manufacturing. This work aims to evaluate the susceptibility of stress corrosion crack (SCC) initiation of bent parts of RVI in high temperature primary water environment. For SCC initiation test, tensile specimens were fabricated from the 90 degree bent plate of Type 304 SS (DT specimen), that is an archived part of a Korean APR1400. After the SCC initiation test, the specimen surface was thoroughly examined by optical and scanning electron microscopy, and compared to the specimen fabricated from the as-received plate of Type 304 SS (AR specimen). The surface observation revealed that SCC initiated on the AR specimen surface in typical intergranular (IG) mode, while SCC on the DT specimen occurred in transgrannular mode as well as IG mode. It was also found that the size and number of SCC on the DT specimen were larger than that on the AR specimen. This was attributable to a strain-hardening during the bending process. To compare the susceptibility of SCC initiation, total crack density (TCD) was calculated from the total crack length divided by the measured area of AR and DT specimens. TCD of DT specimen was 4.6 times higher than AR specimen in average, indicating that higher possibility of degradation of bent parts of RVI for a long-term operation.