• 대한기계학회논문집A
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• 제37권8호
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• pp.1035-1041
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• 2013

본 논문은 KTX 안티롤바 너클부의 동특성 및 구조 안전성 평가를 위해 시험 및 수치적 방법을 사용하였다. 시험적 방법에서는 KTX와 KTX-산천 안티롤바 너클부의 동특성을 비교 평가하기 위해 호남선의 운행환경을 고려한 가속도 및 변형률 데이터를 각각 측정하였으며, 수치적 방법에서는 너클부에 대해 LS-DYNA 3D를 사용하여 구조 안전성 평가를 수행하였다. 이때 해석에 사용된 유한요소모델은 시험과 비교평가를 통해 신뢰성을 검증하였다. 수치해석 결과, 얇은 금속판 및 고무의 적층구조로 이루어진 너클부의 응력 및 속도장이 너클과 커넥팅로드 사이의 상대적 접촉 감소로 인해 두꺼운 강재로만 이루어진 너클부에 비해 좀 더 완화된 경향을 보였다. 그 결과 얇은 금속판과 고무로 구성된 너클 구조가 반복적인 외력 하중하에서 KTX 안티롤바의 탄성거동을 허용하여 동적 거동하의 구조적 안전성을 향상시키기 위한 최선의 방법임을 확인하였다.

• 한국압력기기공학회 논문집
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• 제4권2호
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• pp.13-19
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• 2008

In order to predict a remaining life of a plant, it is necessary to select the components that are critical to the plant life. The remaining life of those components shall be evaluated by considering the aging effect of materials used as well as numerous factors. However, when evaluating reliability of nuclear structural components, some problems are quite formidable because of lack of information such as operating history, material property change and uncertainty in damage models. Accordingly, if structural integrity and safety are evaluated by the deterministic fracture mechanics approach, it is expected that the results obtained are too conservative to perform a rational evaluation of plant life. The probabilistic fracture mechanics approaches are regarded as appropriate methods to rationally evaluate the plant life since they can consider various uncertainties such as sizes and shapes of cracks and degradation of material strength due to the aging effects. The objective of this study is to evaluate the structural integrity for a reactor pressure vessel under the small break loss of coolant accident by applying the deterministic and probabilistic fracture mechanics. The deterministic fracture mechanics analysis was performed using the three dimensional finite element model. The probabilistic integrity analysis was based on the Monte Carlo simulation. The selected random variables are the neutron fluence on the vessel inside surface, the content of copper, nickel, and phosphorus in the reactor pressure vessel material, and initial RTNDT.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2009년도 학술논문요약집
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• pp.255-256
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• 2009

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2011년도 춘계학술대회 논문집
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• pp.1151-1152
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• 2011

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2010년도 추계학술대회 논문집
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• pp.837-838
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• 2010

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집A
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• pp.441-446
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• 2001

In the integral type reactor, SMART, all the major components such as steam generators, pressurizer and pumps are located inside the single reactor pressure vessel. The objective of this study is to evaluate the structural integrity for RPV of SMART under the postulated pressurized thermal shock by applying the finite element analysis. Input data for the finite element analysis were generated using the commercial code I-DEAS, and the fracture mechanics analysis was performed using the ABAQUS. The crack configurations, the crack aspect ratio and the clad thickness were considered in the parametric study. The effects of these parameters on the reference nil-ductility transition temperature were also investigated.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2004년도 추계학술대회논문집
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• pp.958-961
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• 2004

This paper presents a plant control panel model for the analysis. Seismic qualification analysis for the plant control panel is carried out to confirm the structural integrity under the seismic conditions represented by required response spectra(RRS). For the analysis finite element method(FEM) is used. And mode combinations are adopted to obtain the reliability of the spectrum analysis. The analysis results shows that the plant control panel system is designed as a dynamically rigid assembly, without any resonance frequency below 33Hz. The calculated stress of the plant control panel system is much less than yield stress of used steel.

• 한국압력기기공학회 논문집
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• 제19권2호
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• pp.69-74
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• 2023

The paper presents the results investigating the effect of aircraft engine impact location on the intended function evaluation results of spent nuclear fuel transport cask. As a result of the investigation, it is found that the structural integrity is maintained as the maximum accumulated equivalent plastic strain is below the acceptable criterion regardless of the collision location. It is identified that when the aircraft engine collided with the upper part of the transport cask without considering impact limiter the containment performance is weakened compared to when the aircraft engine collided with the central part.

• 방사성폐기물학회지
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• 제3권3호
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• pp.231-236
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• 2005

원전에서 발생하는 건조폐수지를 함유한 고건전성용기(HIC, high integrity container)를 운반하기 위한 HIC 운반용기는 내용물의 높은 방사능으로 인하여 원자력법 및 IAEA의 안전수송규정의 B형 운반용기의 요건을 따라야 하고 정상운반 및 운반사고조건에 대하여 구조적 건전성을 유지하여야 한다. 운반용기는 최대손상을 야기하는 위치에서 단단한 바닥면 위로 9 m 높이에서의 자유낙하충격 및 연강봉 위로의 1 m 높이에서의 낙하충격을 견디어야 한다. HIC 운반용기의 개념설계를 위하여 9 m 자유낙하 및 1 m 파열조건에 대하여 ABAQUS 전산코드를 이용한 3차원동적 구조해석을 수행하고 건전성을 평가하였다.

• KIEAE Journal
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• 제7권4호
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• pp.141-146
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• 2007

It is necessary to guarantee the safety, serviceability and durability of reinforced concrete structures over their service life. However, concrete structures represent a decrease in their durability due to the effects of external environments according to the passage of time, and such degradation in durability can cause structural degradation in materials. In concrete structures, some degradations in durability increase the corrosion of embedded rebars and also decrease the structural performance of materials. Thus, the structural condition assessment of RC materials damaged by corrosion of rebars becomes an important factor that judges needs to apply restoration. In order to detect the damage of reinforced concrete structures, a visual inspection, a nondestructive evaluation method(NDE) and a specific loading test have been employed. However, obscurities for visual inspection and inaccessible members raise difficulty in evaluating structure condition. For these reasons, detection of location and quantification of the damage in structures via structural response have been one of the very important topics in system identification research. The main objective of this project is to develope a methodologies for the damage identification via static responses of the members damaged by durability. Six reinforced concrete beams with variables of corrosion position and corrosion width were fabricated and the damage detections of corroded RC beams were performed by the optimization and the conjugate beam methods using static deflection. In results it is proved that the conjugate beam method could predict the damage of RC members practically.