• 대한기계학회:학술대회논문집
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• 대한기계학회 2008년도 추계학술대회B
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• pp.3059-3066
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• 2008

It is reported that the life of generator stator windings is expected about 30 years and a leak and water absorption phenomena can be progressed by fatigue, vibration, and corrosion. The water-cooled generator stator windings which were operated over 15 years are over 20 units and the mechanical problems such as leak and water absorption were found in the generator stator windings. In this paper, the systematic mechanical integrity evaluation methods which are applied to the water-cooled generator stator windings within the country are introduced.

• 대한기계학회논문집A
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• 제24권8호
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• pp.2083-2090
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• 2000

In order to manage nuclear power plants safely and cost effectively, it is necessary to develop integrity evaluation methodologies for the main components. Recently, the integrity evaluation techniques were broadly studied regarding the license renewal of nuclear power plants which were approaching their design lives. Since the integrity evaluation process requires special knowledges and complicated calculation procedures, it has been allowed only to experts in the specified area. In this paper, an integrity evaluation system for reactor pressure vessel was developed. RVIES(Reactor Vessel Integrity Evaluation System) provides four specific integrity evaluation procedures covering PTS(Pressurized Thermal Shock) analysis, P-T(Pressure-Temperature) limit curve generation, USE(Upper Shelf Energy) analysis and Fatigue analysis. Each module was verified by comparing with published results.

• 한국생산제조학회지
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• 제26권4호
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• pp.436-440
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• 2017

This study evaluated the design and structural integrity of a three-axle bogie frame in a railway freight car through a numerical analysis and an experimental evaluation. A three-axle bogie frame, which supports the weight of the car body and load, is required to transport heavier cargo because two-axle vehicles have structural limitations. Therefore, this study performed a structural analysis and static load tests to evaluate the design and structural integrity of a three-axle bogie frame. The results obtained from the numerical analysis were compared to those of the experiments. For the bogie frame used in the experiments, a failure evaluation was performed using non-destructive methods. The numerical analysis and experimental evaluation were satisfactory for the structural integrity evaluation.

• 한국안전학회지
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• 제29권4호
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• pp.15-22
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• 2014

As the risk of the various external risk was increased, a study on the integrity assessment of the nuclear transport cask was needed. In this paper, an integrity assessment of the nuclear transport cask under the ballistic impact was studied. The projectile with L/D = 5 was used in simulation. The applied head shapes of the projectile were five types such as flat shape, conical shape, hemispherical shape, truncated conical and sliced flat shape, respectively. The range on the velocity of the projectile was 85 m/s to 680 m/s. The cask body of the nuclear transport cask was not penetrated by the projectile speed up to Vprojectile = 510 m/s. As the cask body was penetrated by the all types projectile with Vprojectile = 680 m/s and the cask lead in the nuclear transport cask was collided with the projectile. As the projectile moved to 31.3 mm in the cask lead, the cask lead was not penetrated by the projectile with Vprojectile = 680 m/s. The integrity assessment on the nuclear transport cask under ballistic impact up to Vprojectile = 680 m/s was obtained.

• 대한기계학회논문집A
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• 제20권5호
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• pp.1468-1476
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• 1996

Surface integrity is dictated by the fabrication process of the metal part. In this work, steel specimens were prepared under various mechine conditions to achieve different degrees of deformation state. The tribological characteristics of the speciments were tested using a pin-on-disk type apparatus and other surface characterization tools. It is shown that though frictional characteristics are similar, the wear rate is significantrly affected by the properties of the surface. In the case of steel, surface cracks resulted in high wear despite the relatively high hardness of the specimen. Also, the sliding action were found to reduce the residual stress on the surface. These results indicate that there is a strong relationship between surface integrity and the tribological properties of steel, and therefore the machining condition should be optimized woth respect to tribological performance of a steel part.

• Composites Research
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• 제30권6호
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• pp.338-342
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• 2017

본 논문에서는 원통형 복합재 격자구조체의 구조안전성 평가 기법에 대해 연구를 수행하였다. 구조안전성 평가는 유한요소해석을 통해 수행하였다. 구조안전성 평가를 위한 최적의 유한요소를 확인하기 위해 원통형 복합재 격자구조체 유한요소모델은 빔, 쉘 그리고 솔리드 요소를 사용해 생성하였다. 쉘과 솔리드 모델의 유한요소 해석결과는 서로 유사하게 발생되었다. 그러나 빔 모델의 경우, 쉘과 솔리드 모델의 결과와 큰 차이가 발생하였다. 이것은 빔 요소가 원통형 복합재 격자구조체 섬유 비교차부의 기계적 물성저하를 고려하지 못하기 때문이다. 원통형 복합재 격자구조체의 구조안전성 평가를 위한 유한요소해석은 쉘 또는 솔리드 요소를 사용해야 하는 것을 확인하였다.

• Journal of Advanced Marine Engineering and Technology
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• 제40권9호
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• pp.780-785
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• 2016

선박의 연료로 이용되는 중유는 지구 온난화를 일으키는 유해가스를 배출한다. 이를 저감하기 위해 친환경선박으로 표현되고 있는 녹색선박이 등장하게 되었고, 천연가스를 연료로 하는 액화천연가스(LNG) 연료 선박이 대표적인 사례이다. 본 논문에서는 LNG 선박에 사용되는 극저온 환경에서 고압 하중을 받는 기화기와 출입구 배관의 구조 건전성을 ASME 코드에 따라 평가하고 실용화한 최초의 사례이다. 기화기와 배관은 유한요소법을 사용하여 구조해석을 수행하였다. 기화기는 등가응력을 바탕으로 ASME Section VIII Division 2에 제시된 허용응력과 비교하여 건전성 평가를 수행하였고, 배관은 성분별 응력을 조합하여 ASME B31.3에 제시된 허용응력과 비교 및 건전성 평가를 수행하였다. 각 하중에 대한 구조물들의 응력 결과는 허용응력 범위 이내에 있으므로 구조적 건전성을 유지하는 것으로 평가되었다.

• Tribology and Lubricants
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• 제35권3호
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• pp.169-175
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• 2019

In lithium-ion batteries (LIBs), the stress induced by the volume change of an electrode during charge-discharge processes may often cause the mechanical integrity of the electrode to degrade. Polymer binders with enhanced mechanical properties are preferred for improved mechanical integrity and cycling stability of the electrode. In addition, given that sliding and shearing between the polymer binder and components in the electrode may readily occur, frictional and adhesion characteristics of the polymer binder may play a critical role in the mechanical integrity of the electrode. In this study, frictional and adhesion characteristics of polyacrylonitrile (PAN) and polyvinylidene fluoride (PVDF) were investigated using a colloidal probe atomic force microscope. Friction loops were obtained under various normal forces ranging from 0 to 159 nN in air and electrolyte and then the interfacial shear strengths of PAN and PVDF in air were calculated to be $1.4{\pm}0.5$ and $1.3{\pm}0.3MPa$, respectively. The results show that in electrolyte, interfacial shear strength of PAN decreased slightly ($1.2{\pm}0.2MPa$), whereas that of PVDF decreased drastically ($0.06{\pm}0.01MPa$). Decreases in mechanical properties and adhesion in electrolyte may be responsible for the decrease in interfacial shear strength in electrolyte. The findings from this study may be helpful in developing polymer binders to improve the mechanical integrity of electrodes in LIBs.

• 대한기계학회논문집A
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• 제28권6호
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• pp.663-669
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• 2004

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

• 대한기계학회논문집A
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• 제28권3호
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• pp.289-295
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• 2004

Pressure tubes are major component of nuclear reactor, but only selected samples are periodically examined due to numerous numbers of tubes. Current in-service inspection result show there is high probability of flaw existence at uninspected pressure tube. Probabilistic analysis is applied in this study for the integrity assessment of uninspected pressure tube. All the current integrity evaluations procedures are based on conventional deterministic approaches. So it is expected that the results obtained are too conservative to perform a rational evaluation of lifetime. More realistic failure criteria, based on FAD are also proposed for the probabilistic analysis. As a result of this study failure probabilities for various conditions are calculated, and examined application of FAD and LBB concept.