• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2003년도 춘계학술발표대회 개요집
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• pp.257-259
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• 2003

Sulfide Stress Corrosion Cracking(SSCC) of welded Steel pipe has been investigated. A specimens are stressed into the synthetic sea water saturated with H$_2$S. Therefore SSCC occur at the hardnest point. we are discusses the test methods used for laboratory corrosion testing of welded steel pipe and the results of test.

• 한국정밀공학회지
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• 제19권11호
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• pp.174-182
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• 2002

The integrity evaluation of pressure tube is essential for the safety of CANDU reactor, and integrity must be assured when flaws or contacts between pressure tube and surrounding calandria tube are found. In order to complete the integrity evaluation, not only complicated and iterative calculation procedures but also a lot of data and knowledge are required. For this reason, an integrity evaluation system, which provides an efficient way of the evaluation with the help of attached databases, was developed. The developed system was built on the basis of ASME Sec.？ and FFSG issued by the AECL, and applicable for the evaluation of blister, sharp flaw and blunt notch. Delayed hydride cracking and blister evaluation modules are included in the general flaw and notch evaluation module. In order to verify the developed system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.

• 문화기술의 융합
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• 제10권1호
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• pp.363-368
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• 2024

선박, 해양구조물 또는 해상풍력 발전설비 하부구조와 같이 해양환경에서 사용되는 강구조물은 부식이 쉽게 발생한다. 본 연구에서는 실험을 통하여 희생전극으로 많이 사용되는 아연전극의 방식전위와 동등한 -1050mV vs. SCE에서 환경하중에 기인하는 부식피로균열 진전특성에 대하여 고찰하였다. 이를 위하여 본 연구에서는 -1050mV vs. SCE의 음극방식이 해수환경중의 피로균열 진전에 미치는 영향에 대해 합성해수중에서 파랑주기를 고려하여 실험적 고찰을 실시하였다. 음극방식에 의한 방식법은 부식을 차단하지만 과도한 방식은 화학반응에 의하여 수소를 발생시키며, 또한 석회질퇴적물을 발생시킨다. 피로균열진전율은 실험초기에는 해수부식환경하에서의 진전율보다 빠른구간이 나타났다. 그리고 균열길이가 증가하여 응력확대계수 K가 커질수록 균열의 진전율은 해수중의 피로균열진전율보다 느려지는 현상이 나타났다. 그러나 대기중의 균열진전속도보다는 항상 빠른 진전속도를 나타내었다.

• 대한기계학회논문집A
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• 제38권2호
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• pp.167-175
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• 2014

가동중검사 동안 가압중수로 압력관에서 탐지된 베어링 패드 프레팅 결함, 이물질 프레팅 결함 등 체적결함에 대해서는 CSA N285.8-05 에 따라 탄성 응력집중계수 수식을 이용하여 피로균열 및 수소지연균열이 개시되는 것을 평가하여야 한다. CSA N285.8-05 에는 이물질 프레팅 결함에 대해서는 선형파괴역학 기반한 개략적인 수식만이 제시된다. 본 연구에서는 이러한 이물질 프레팅 결함에 대해 2 차원 유한요소 해석과 일부 수정된 Kinectrics 사의 공학적 절차를 통해 이물질 프레팅 결함의 기하학적 특성이 좀더 상세히 고려된 탄성 응력집중계수 수식을 도출하였다. 도출된 수식을 적용한 결과와 3 차원 유한요소 해석 결과를 비교한 결과, 도출된 수식은 유한요소 해석과 잘 일치하는 결과를 얻을 수 있음을 확인하였다.

• Journal of Welding and Joining
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• 제13권4호
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• pp.46-54
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• 1995

The cold cracking susceptibility of a variety of weld metals deposited by GMAW with several kinds of commercial solid wires for high strength-toughness steel was investigated. G-BOP test and LB-TRC test were carried out to study the effects of preheat, chemical composition and hydrogen level on the weld metal cold cracking. The results obtained are as follows. 1) 10% CPT obtained by G-BOP test was the most valuable criteria for evaluating the cold cracking susceptibility of weld metals compared with percentage of cracking at room temperature and crack free temperature, and it had good correlation with the results of LB-TRC test. 2) Cold cracking susceptibility of weld metals was high in the row of MG100A, MG100C, MG100D and MG100B. Welds deposited with MG130 and MG80 showed similar icidents of cracking with MG100C and MG100B respectively, even though their strength levels were different. 3) Diffusible hydrogen level in weld metals which has good relation with hydrogen content in wire itself was the most critical factor for controlling the cold cracking susceptibility of weld metal.

• Journal of Welding and Joining
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• 제7권2호
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• pp.49-59
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• 1989

The effect of non-metallic inclusions on the HAZ hydrogen induced cracking was investigated. Quench and temper high tensile strength steels containing various sulphur contents were employed. The sulphur contents range between 0.007% and 0.040%. Non-metallic inclusions were mainly MnS type sylphide and Mn-Al-Si type. The sensitivity of HAZ delayed cracking was evaluated by implant testing. Diffusible hydrogen content was varied by controlling the moisture absorbing condition of manual arc welding electrodes. The one was asreceived condition, the other was dipping the electrodes in the water for ten minutes. The main results obtained were as follows; 1) The results of implant test showed that critical stress increased with increasing S content up to 0.013%. But steel containing 0.040%S showed lower critical stress than that of 0.013% S. These result suggest that there will be optimum S content to prevent HAZ delayed cracking of high strength steels. 2) Under the lower D.H.C. level, critical stress was increased with rolling reduction, but higher D.H.C. level, effect of rolling reduction was not recognized.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.229-229
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• 2004

원자력발전소에서 원자로 냉각재 중의 용존산소 제어는 원자로 냉각재 계통에서의 전면 부식과 다양한 형태의 응력부식균열(SCC)를 완화시키는데 기여한다. 원자로 냉각재 계통내에 용존 되어있는 산소는 발전소 기동 시에는 하이드라진($N_2H_4$)을 넣거나 인위적 배기를 통해 제거하고, 정상운전 중에는 체적제어탱크(VCT)에 수소를 가압하여 제거시킨다. 계통내로 유입되는 용존산소를 최대한 억제하기 위하여 대부분의 원자력발전소는 원자로 보충수 탱크 상층부에 질소를 주입하여 탱크로 유입되는 공기를 차단하고 있으나, 이 과정에서 일부 수중에 용해되어 들어가는 질소는 계통 내에서 NH$_3$를 형성하여 화학체적제어계통(CVCS)의 이온교환 수지탑에 치환됨으로서 기포화 되어있는 Li을 계통으로 빠져나오게 하여 계통 pH에 영향을 미친다.(중략)

• 한국해양공학회지
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• 제4권1호
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• pp.88-100
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• 1990

Among the test methods to evaluate stress-corrosion cracking(SCC) on the basis of fracture mechanics, constant displacement(bolt) loading method using modified-WOL specimen is practically convenient. In this test method, compliance formula is generally required to calculate load(consequently $K_{ISCC}$). There are many problems in using the analytic compliance formula to calculate $K_{ISCC}$, so we had proposed the experimental $K_{ISCC}$ evaluation technique in the previous report. This study has employed the slightly altered configuration of modified-WOL specimen made of weldable structural stee(BS360-50D). With these specimens, stress-corrosion tests have been performed in $H_2S$ gas saturated 20% HCl solution. Through the test, the problems as mentioned earlier have been discussed again, and the proposed evaluation technique has been verified. And the stress-corrosion cracks and hydrogen blisters have been investigated in the initiation step with the aids of metallurgical micrographs, SEM fractographs, and EPMA analysis. The inclusions segregated in the mid-thickness region traps hydrogen to produce the hydrogen blistering. The applied or residual stress does not contribute the occurrence of the blister. Hydrogen absorbed into the mid-thickness region is consumed to produce the blistering so that stress-corrosion crack could hardly be detected at that region. The stress-corrosion cracks initiate from the inclusions and propagate in radial pattern. And the initiation site is remote from the crack tip and is inclined from the crack plane, which is assumed to be caused by the triaxial stress and the amount of the absorbed hydrogen.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회A
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• pp.114-119
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• 2007

Sulfide stress cracking (SSC) of materials exposed to oilfield environment containing hydrogen sulfide $(H_{2}S)$ has been recognized as a materials failure problem. Laboratory data and field experience have demonstrated that extremely low concentration of $H_{2}S$ may be sufficient to lead to SSC failure of susceptible materials. In some cases, $(H_{2}S)$ can act synergistically with chlorides to produce corrosion and cracking failures. SSC is a form of hydrogen embrittlement that occurs in high strength steels and in localized hard zones in weldment of susceptible materials. In the heat-affected zones adjacent to welds, there are often very narrow hard zones combined with regions of high residual stress that may become embrittled to such an extent by dissolved atomic hydrogen. On the base of understanding on sulfide stress cracking and its mechanism, SSC resistance for the several materials, those are ASTM A106 Gr B using in the oil industries, are evaluated.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 추계학술대회논문집A
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• pp.843-848
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• 2000

The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle and it's containment vessel. If a flaw is found during the periodic inspection from the pressure tubes, the integrity evaluation must be carried out, and the safety requirements must be satisfied for continued service. In order to complete the integrity evaluation, complicated and iterative calculation procedures are required. Besides, a lot of data and knowledge for the evaluation are required for the entire integrity evaluation process. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached databases, was developed. The developed system was built on the basis of ASME Sec. XI and FFSG(Fitness For Service Guidelines for zirconium alloy pressure tubes in operating CANDU reactors) issued by the AECL, and covers the delayed hydride cracking(DHC). Various analysis methods are provided for the integrity evaluation of pressure tube. In order to verify the developed system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.