• Structural Engineering and Mechanics
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• 제14권2호
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• pp.209-221
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• 2002

In this paper a fracture criterion is proposed for cracked cylindrical samples of high-strength prestressing steels of different yield strength. The surface crack is assumed to be semi-elliptical, a geometry very adequate to model sharp defects produced by any subcritical mechanism of cracking: mechanical fatigue, stress-corrosion cracking, hydrogen embrittlement or corrosion fatigue. Two fracture criteria with different meanings are considered: a global (energetic) criterion based on the energy release rate G, and a local (stress) criterion based on the stress intensity factor $K_I$. The advantages and disadvantages of both criteria for engineering design are discussed in this paper on the basis of many experimental results of fracture tests on cracked wires of high-strength prestressing steels of different yield strength and with different degrees of strength anisotropy.

• 대한기계학회논문집A
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• 제34권5호
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• pp.629-635
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• 2010

SGBEM-FEM 교호법이 Nikishkov, Park 및 Atluri 에 의하여 제안되었었다. 제안된 방법을 사용하면 임의 형태의 평면 혹은 비평면 삼차원 균열에 대하여 복합 모드의 응력강도계수를 구할 수 있다. 그러나 현장에서의 적용을 위해서는 이 방법의 정확성 및 신뢰성에 대한 검토가 더욱 필요하다. 따라서 본 논문에서는 응력강도계수에 영향을 주는 주요한 몇 가지 인자를 검토하였다. 그리고 원통의 내부 및 외부에 존재하는 원주방향 표면균열에 대한 응력강도계수를 구하여 기존의 해와 비교하였다. 그 결과 SGBEM-FEM 교호법은 이들 균열에 대하여 정확한 해를 주고 있음을 확인하였다.

• 대한조선학회논문집
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• 제60권4호
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• pp.213-221
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• 2023

The demand for Liquefied Natural Gas (LNG) carriers and LNG-fueled ships has significantly increased in recent years due to the sulfur-oxide emission regulations by the International Maritime Organization (IMO). The main goal of this paper is to introduce the process for the Engineering Critical Assessment (ECA) of IMO independent type-B cargo tanks made from 9% nickel alloy. A methodology proposed by the British Standard was used to conduct ECA for any structure with initial flaws. Based on this standard, a Matlab code was developed to perform ECA. Coarse mesh Finite Element Analysis (FEA) was performed on an independent type-B LNG cargo tank with a capacity of 15,000 m³. The location with the highest development of maximum principal stress was identified at the bottom of the cargo tank. Fine mesh FEA was performed to obtain the stress range required for ECA. The dynamic cargo tank loads used for FEA were determined using some ship rules presented by Det Norske Veritas. As a result of performing a 20-year long-term crack propagation analysis with a semi-elliptical surface crack, the fracture-to-yield ratio exceeded the Fracture Assessment Line (FAL) and some structural reinforcement was necessary. Performing a 15-day short-term crack propagation analysis, the fracture-to-yield ratio remained within the FAL, and no significant LNG leaks were expected. This paper is believed to provide a guide for performing ECA of LNG cargo tanks in the future by providing the basic theory and application sample necessary to perform ECA.

• 한국강구조학회 논문집
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• 제10권3호통권36호
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• pp.423-435
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• 1998

본 연구에서는 기존의 강교에서 흔하게 발견되고 있는 맞대기 용접부의 용입불량으로 인한 부재의 피로강도 저하도를 정량적으로 평가하고자 하였다. 이를 위하여 강교량의 재료로 널리 사용되고 있는 SWS490강으로 제작된 완전용입 및 용입깊이가 서로 다른 불완전용입 맞대기 용접시험편을 대상으로 일정진폭하중시험을 수행하여 S-N선도를 산출하고 이를 비교 검토하였으며, 파괴역학적 방법을 이용하여 불완전용입 용접재의 피로수명을 계산하였다. 본 연구의 결과로서, 완전용입 용접재의 경우 AASHTO의 피로강도등급선도와의 비교에서 피로한도값은 A등급보다 높은 값을 보였고, S-N선도의 기울기는 5.57로 매우 높게 나타났다. 불완전용입 용접재의 경우 불완전용입깊이 D가 증가함에 따라 피로강도가 감소하는데, D=14.7mm인 경우 AASHTO의 E'등급보다 낮게 나타난다. 불완전용입 용접재의 파손거동에서 피로균열은 내부 용접루트 선단부에서 a/c가 매우 작은 반타원형 표면균열의 형태로 발생하고, 시험체의 두께방향으로 진전하여 최종파손을 유발한다. 파괴역학적 방법을 이용한 불완전용입 용접재의 피로수명을 평가하기 위하여 3차원 반타원형 균열형상에 대한 응력확대계수 K를 유한요소해석으로 구하였다. 여기서 얻어진 K값과 실험으로 얻어진 Paris식의 상수를 이용하여 불완전용입 용접재의 피로수명을 계산하여 비교하였다. 그리고 실제 불완전용입 맞대기용접부의 파손으로 붕괴사고가 발생한 성수대교의 수직재에 본 연구결과를 적용하여 피로수명을 계산해 보았다.

• 한국가스학회지
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• 제27권3호
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• pp.116-122
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• 2023

저탄소 친환경에너지 정책이 진행으로 인해 수소 공급을 위한 수소충전소의 증가됨에 따라 사고발생 위험도 커지고 있다. 실제 압력용기는 제조과정에서 발생할 수 있는 노치와 기공, 개재물 등의 결함이 존재할 수 있다. 따라서 내압이 작용하고 있는 압력용기에 균열이 존재할 경우에 대한 압력용기의 건전성을 평가하는 것은 필요하다. 본 연구에서는 표면균열이 있는 수소충전용 압력용기의 구조안전성을 평가하기 위해 3차원 유한요소해석을 이용하였으며, 표면균열의 형상은 일반적으로 많이 사용되는 반타원 형상을 적용하여 균열의 형상 및 응력비에 대한 균열진전 특성을 비교하였다. 향후, 이러한 결과를 이용하여 파괴역학을 고려한 압력용기의 잔존수명 예측에 활용할 예정이다.

• 한국안전학회지
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• 제21권4호
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• pp.33-41
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• 2006

Material degradation should be considered to assess integrity and residual life of high temperature equipments. However, the property data reflecting degradation are not sufficient for practical use. In this study measuring properties for 1Cr-1Mo-0.25V forging steel generally used for turbine rotor was carried out. Degradation was simulated by isothermal ageing. heat treatment and variation of microstructure was observed. Mechanical properties such as tensile strength, impact energy, hardness and fracture toughness were measured. Assuming a semi-elliptical surface crack at the bore hole in a turbine rotor, material risk was estimated by using the aged material property data obtained in this study. Safety margin was decreased and life of the rotor was exhausted. This procedure can be used in assessing the residual life of a turbine rotor due to material degradation.

• 대한기계학회논문집A
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• 제26권4호
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• pp.653-659
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• 2002

This paper describes a probabilistic fracture mechanics(PFM) analysis based on Monte Carlo(MC) simulation. In the analysis of CANDU pressure tube, the depth and aspect ratio of an initial semi-elliptical surface crack, a fracture toughness value and delayed hydride cracking(DHC) velocity are assumed to be probabilistic variables. As an example, some failure probabilities of piping and CANDU pressure tube are calculated using MC method with the stratified sampling MC technique, taking analysis conditions of normal operations. In the stratified MC simulation, a sampling space of probabilistic variables is divided into a number of small cells. For the verification of analysis results, a comparison study of the PFM analysis using other commercial code is carried out and a good agreement was observed between those results.

• 한국정밀공학회지
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• 제27권8호
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• pp.42-47
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• 2010

In this paper, the characteristics of contact surface damage due to fretting in a press-fitted shaft below the fretting fatigue limit are proposed by experimental methods. A series of fatigue tests and interrupted fatigue tests of small scale press-fitted specimen were carried out by using rotating bending fatigue test machine. Macroscopic and microscopic characteristics were examined using scanning electron microscope (SEM), optical microscope or profilometer. It is found that fretting fatigue cracks were initiated even under the fretting fatigue limit on the press-fitted shafts by fretting damage. The fatigue cracks of press-fitted shafts were initiated from the edge of contact surface and propagated inward in a semi-elliptical shape. Furthermore, the fretting wear rates at the contact edge are increased rapidly at the initial stage of total fatigue life. After steep increasing, the increase of wear rate is nearly constant under the load condition below the fretting fatigue limit. It is thus suggested that the fretting wear must be considered on the fatigue life evaluation because the fatigue crack nucleation and propagation process is strongly related to the evolution of surface profile by fretting wear in the press-fitted structures.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2010년도 춘계학술발표대회 초록집
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• pp.43-46
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• 2010

As the nuclear power plant has been constructed continuously for several decades in Korea, the welding technology for components manufacturing and installation has been improved largely. Standardization for weld test and qualification was also established systematically according to the concerned code. The welding for the main components requires the high reliability to keep the constant quality level, which means the repeatability of weld quality. Therefore the weld process qualified by thorough test and evaluation is able to be applied for manufacturing. Narrow gap SAW and GTAW process are usually applied for girth seam welding of pressure vessel like Reactor vessel, steam generator, and etc. For the surface cladding with stainless steel and Inconel material, strip welding process is mainly used. Inside cladding of nozzles is additionally applied with Hot wire GTAW and semi-auto welding process. Especially the weld joint having elliptical weld line on curved surface needs a specialized weld system which is automatically rotating with adjusting position of the head torch. The small sized pipe, tube, and internal parts of reactor vessel requests precise weld processes like an automatic GTAW and electron beam welding. Welding of dissimilar materials including Inconel690 material has high possibility of weld defects like a lack of fusion, various types of crack. To avoid these kinds of problem, optimum weld parameters and sequence should be set up through the many tests. As the life extension of nuclear power plant is general trend, weld technologies having higher reliability is required gradually. More development of specialized welding systems, weld part analysis and evaluation, and life prediction for main components should be taken into a consideration extensively.

• 한국강구조학회 논문집
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• 제12권2호통권45호
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• pp.111-122
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• 2000

이 연구에서는 덮개판 형상이 피로특성에 미치는 영향을 정량적으로 평가하기 위해서 강교량을 구성하는 구조세목 중 덮개판 필렛용접부를 대상으로 일련의 피로실험을 실시하였다. 피로실험결과 덮개판 형상에 따라 피로강도에 다소 차이를 나타내고 있었으나 국내 및 외국의 피로설계기준을 만족함을 알 수 있었다. 또한 비치마크실험결과로부터 피로균열 발생점은 용접지단부의 형상에 밀접하게 관련되어 있음을 확인할 수 있었으며, 용접지단부의 여러 곳에서 동시다발적으로 발생한 피로균열이 반타원형의 표면균열의 형태로 성장하고 이 균열이 서로 합체되어 관통균열의 형태로 성장함으로써 결국 파단에 이르렀다. 한편, 파괴역학적 해석결과로부터 기존의 제안식 및 유한요소해석에서 구한 균열보정 계수 중기하학적형상보정계수가 가장 지배적임을 알 수 있었으며, 피로균열성장속도와 유한요소해석에서 구한 응력확대계수범위 사이의 관계로부터 덮개판 필렛용접부의 피로수명을 산정 할 수 있었다.