• 대한조선학회 특별논문집
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• 대한조선학회 2005년도 특별논문집
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• pp.22-30
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• 2005

Sloshing loads, produced by the violent liquid free-surface motions inside the cargo tank have become an important design parameter in ship building industry since there have been demands for the increased sizes of the cargo containment system of LNG carriers. In this study, sloshing impact pressure acting on the shell of the spherical cargo tank of an LNG carrier as well as dynamic pressure and flow behavior around the pump tower located at the center of the tank have been calculated. Comparative numerical sloshing simulations for a spherical LNG tank using 2-D LR.FLUIDS which is based on the finite difference method and 3-D MSC.DYTRAN which is capable of calculating nonlinear fluid-structure interaction have been carried out. A method of calculating sloshing-induced dynamic loads and the subsequent structural strength analysis for pump tower of a spherical LNG carrier using MSC. DYTRAN and MSC.NASTRAN have been presented.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2011년도 정기 학술대회
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• pp.527-530
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• 2011

전 세계적인 LNG 수요 증가에 따라 LNG 운반선의 대형화 및 극한 환경의 항로 선택이 불가피해지고 있다. 이러한 상황에서 LNG의 슬로싱 현상에 따른 화물창의 구조적 안정성 여부가 큰 이슈거리로 떠오르고 있다. 슬로싱 현상에 의한 구조 안전성을 평가하는 가장 이상적인 방법은 유체 영역과 탱크의 복합적인 상호 작용을 완벽하게 구현하는 것이다. 하지만 과도한 계산 시간과 결과의 정확성이 확보되지 못한 상황에서 LNG 운반선 화물창의 안전성 평가에 적용하기에는 문제가 있다. 많은 연구 단체에서는 불규칙적인 슬로싱 압력 신호를 삼각파 등의 형태로 이상화하여 구조해석에 적용하고 있지만 이 또한 유체의 압축성 및 비선형성을 고려하는데 한계를 드러내고 있다. 본 연구에서는 슬로싱 하중을 받는 구조의 안전성을 평가함에 있어 쌍방향(2-way) FSI(Fluid-Structure Interaction)의 과도한 해석 시간 및 수렴의 어려움을 보안하고 유체의 비선형성을 고려할 수 있는 단 방향(1-way) FSI 기법을 이용하는 절차를 제안하고자 한다.

• Nuclear Engineering and Technology
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• 제26권2호
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• pp.257-264
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• 1994

원자력발전소 중대사고시 용융된 노심과 잔류냉각수가 증기폭발을 일으켜 원자로 격납용기의 건전성을 위협할 수 있다. 본 연구에서는 증기폭발을 모사할 수 있는 실험 장치를 제작하고, 물과 프레온을 사용하여 증기폭발실험을 수행하였다. 이때 고속카메라를 사용하여 폭발현상을 관측하였고, 동압측정기와 압력분출관을 이용하여 생성되는 폭발압력과 기계적인 에너지를 계측하였다. 이를 토대로 증기폭발의 중요인자들(물의 온도, 물의 주입속도, 물의 주입 시간, 그리고 냉매의 깊이)에 대한 민감도 분석을 수행하였다. 그리고, 압력용기 바닥의 구조물이 용융/냉각재의 반응에 미치는 영향을 살펴보기위하여 실험용기 내부에 그리드를 설치하여 폭발실험을 실시하였다. 물/프레온의 폭발실험에서 계측된 기계적에너지를 이용한 에너지효율은 0.5∼l.6%인 것으로 계산되었다.

• Structural Engineering and Mechanics
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• 제81권6호
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• pp.781-790
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• 2022

The present paper describes a general procedure of the structural safety assessment for the independent type C tank of LNG bunkering ship. This strength assessment procedure consists of two main scheme, global Finite Element Analysis (FEA) model primarily for hull structure assessment and detailed LNG Tank structures FEA model including the cylindrical tank itself and saddle-support structures. Two kinds of mechanism are used, fixed and slides constraints in fore and rear of the saddle-support structures that result in a variation of the reaction forces. Finite Element (FE) analyses have been performed and verified by the strength acceptance criteria to evaluate the safety adequacy of yielding and buckling of the hull and supporting structures. The detail of FE model for an LNG type C tank and its saddle supports was made, which includes the structural members such as cylindrical tank shell, ring stiffeners, swash bulkhead, and saddle supports. Subsequently, the FE buckling analysis of the Type C tank has been performed under external pressure following International Gas Containment (IGC) code requirements. Meanwhile, the assessment is also performed for yielding and buckling strength evaluation of the cylindrical LNG tank according to the PD 5500 unfired fusion welded pressure vessels code. Finally, a complete procedure for assessing the structural strength of 500 CBM LNG cargo tank, saddle support and hull structures have been provided.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1518-1527
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• 2023

A method was proposed for in-situ evaluating the thickness and resistivity of the oxide/hydroxide film formed on the surface of aluminum alloy exposed to sump water formed in the containment after a loss-of-coolant accident. The evaluation entailed fitting a model for the film impedance, which has film thickness and other variables describing the resistivity profile of the film along its thickness direction as fitting parameters, to the practically measured electrochemical impedance data. The obtained resistivity profiles implied that the films formed at pHs_25℃ 7, 8, 9, 10, and 11 all had a duplex structure; compared to the outer layer in contact with the solution, the inner layer of the film had a much higher resistivity and was inferred to be denser and provide most of the protectiveness of the film. Both the thickness and the total resistance of the film decreased with the increasing solution pH_25℃, suggesting that the films formed in more alkaline solutions had less protectiveness against corrosion, consistent with the increasing aluminum alloy corrosion rates previously identified.

• 한국농공학회지
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• 제39권4호
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• pp.106-113
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• 1997

Dynamic loading of structures often causes excursions of stresses well into the inelastic range, and the influence of the geometric changes on the dynamic response is also significant in many cases. Therefore, both material and geometric nonlinearity effects should be considered in case that a dynamic load acts on the structure. A structure in a nuclear power plant is a structure of importance which puts emphasis on safety. A nuclear container is a pressure vessel subject to internal pressure and this structure is constructed by a reinforced concrete or a pre-stressed concrete. In this study, the material nonlinearity effect on the dynamic response is formulated by the elasto-viscoplastic model highly corresponding to the real behavior of the material. Also, the geometrically nonlinear behavior is taken into account using a total Lagrangian coordinate system, and the equilibrium equation of motion is numerically solved by a central difference scheme. The constitutive relation of concrete is modeled according to a Drucker-Prager yield criterion in compression. The reinforcing bars are modeled by a smeared layer at the location of reinforcements, and the steel layer model under Von Mises yield criteria is adopted to represent an elastic-plastic behavior. To investigate the dynamic response of a nuclear reinforced concrete containment structure, the steel-ratios of 0, 3, 5 and 10 percent, are considered. The results obtained from the analysis of an example were summarized as follows 1. As the steel-ratio increases, the amplitude and the period of the vertical displacements in apex of dome decreased. The Dynamic Magnification Factor(DMF) was some larger than that of the structure without steel. However, the regular trend was not found in the values of DMF. 2. The dynamic response of the vertical displacement and the radial displacement in the dome-wall junction were shown that the period of displacement in initial step decreased with the steel-ratio increases. Especially, the effect of the steel on the dynamic response of radial displacement disapeared almost. The values of DMF were 1.94, 2.5, 2.62 and 2.66, and the values increased with the steel-ratio. 3. The characteristics of the dynamic response of radial displacement in the mid-wall were similar to that of dome-wall junction. The values of DMF were 1.91, 2.11, 2.13 and 2.18, and the values increased with the steel-ratio. 4. The amplitude and the period of the hoop-stresses in the dome, the dome-wall junction, and the mid-wall were shown the decreased trend with the steel-ratio. The values of DMF were some larger than those of the structure without steel. However, the regular trend was not found in the values of DMF.

• 한국지진공학회논문집
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• 제9권6호
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• pp.13-19
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• 2005

원자력발전소의 기기, 배관 시스템과 같은 부속구조물의 동적 응답을 먼기 위해 사용되는 층응답스펙트럼은 일반적으로 주구조물과 부속구조물의 동적 상호작용이 반영되지 않고 만들어진다. 본 연구에서는 기기와 구조물의 동적 상호작용이 고려된 해석을 통해 층응답스펙트럼을 생성시키는 해석법을 기술하였다. 이 방법은 기기를 모사하는 단자유도계와 기기가 놓여있는 구조물의 임피던스로 분할되는 부분구조 해석법을 적용하여 기기의 응답을 구한다. 단자유도계의 진동수, 감쇠비 및 질량 특성을 변화시키면서 최대 동적 응답을 계산함으로써 일련의 층응답스펙트럼을 작성한다. 전형적인 원자력발전소의 원자로 구조물에서 본 방법을 고려한 층응답스펙트럼과 기기를 포함한 전체 해석으로부터 작성된 층응답스펙트럼과 비교함으로써 본 연구의 타당성을 확인하였다. 기기-구조물 상호작용 효과를 확인하기 위하여 구조물 질량의 1% 이내인 기기에 대하여 기술된 방법과 기존 방법을 각각 적용하여 최대 응답값을 비교하였다. 그 결과 지배 진동수 부근에서 기기-구조물 상호작용을 고려한 응답이 그렇지 않은 경우인 기존방법의 응답에 비하여 저감되는 현상을 보였다.

• 한국해양공학회지
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• 제28권6호
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• pp.517-526
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• 2014

The leakage of cryogenic LNG through cracks in the insulation membrane of an LNG carrier causes the hull structure to experience a cold spot as a result of the heat transfer from the LNG. The hull structure will become brittle at this cold spot and the evaporated natural gas may potentially lead to a hazard because of its flammability. This paper presents a computational model for the LNG flow and heat diffusion in an LNG insulation panel subject to leakage. The temperature distribution in the insulation panel and the speed of gas diffusion through it are simulated to assess the safety level of an LNG carrier subject that experiences a leak. The behavior of the leaked LNG is modeled using a multiphase flow that considers the mixture of liquid and gas. The simulation model considers the phase change of the LNG, gas-liquid multiphase interactions in the porous media, and accompanying rates of heat transfer. It is assumed that the NO96-GW membrane storage is composed of glass wool and plywood for the numerical simulation. In the numerical simulation, the seepage, heat diffusion, and evaporation of the LNG are investigated. It is found that the diffusion speed of the leakage is very high to accelerate the evaporation of the LNG.

• 대한조선학회논문집
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• 제57권3호
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• pp.168-174
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• 2020

Recently, the size of Liquified Natural Gas (LNG) carriers has been increasing, in turn increasing the load generated during operation. To handle this load, the thickness of LNG Cargo Containment Systems (CCSs) should be increased. Despite increasing the thickness of LNG CCSs, a secondary barrier is still used in conventional thickness. Therefore, the mechanical performance of the existing secondary barrier should be verified. In this study, tensile test of the secondary barrier was performed to evaluate mechanical properties under several low- and cryogenic-temperature conditions considering LNG environment, and in each fiber direction considering that the secondary barrier is composed of anisotropic composite materials depending on the glass fibers. Additionally, the coefficient of thermal expansion was measured by considering the degradation of the mechanical properties of the secondary barrier caused by the generated thermal stress during periodical unloading. As a result, the mechanical performance of secondary barrier in the Machine Direction (MD) was generally found to be superior than that in the Transverse Direction (TD) owing to the warp interlock structure of the glass fibers.

• 대한토목학회논문집
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• 제39권3호
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• pp.369-380
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• 2019

PSC 구조물에 폭발과 같은 극한하중이 짧은 시간 동안 발생하게 되면 급작스러운 파괴와 그로 인한 수많은 인명 및 재산피해를 발생시킨다. 하지만 원전격납구조물, 가스탱크와 같은 PSC 구조물의 경우 방호 및 방재개념이 포함된 구조설계가 적용되지 않은 실정이며, 특히, 구조물 내부에서 발생하는 폭발압력하중은 피해규모가 외부폭발에 비해 훨씬 크기 때문에 내부폭발하중에 대한 검증은 반드시 필요하다. 따라서, 본 연구에서는 원전격납구조물의 내부폭발에 대한 저항성능을 검토하기 위해 이방향 프리스트레스트 콘크리트 축소모형을 제작하였다. 내부폭발 실험은 22.68, 27.22, 31.75 kg (50, 60, 70 lbs)의 ANFO 폭약을 이용하여 시편으로부터 1,000 mm의 거리에서 폭발시켰으며, 압력하중, 처짐, 변형률, 균열형상, 긴장력 변화 등의 데이터를 분석하였다. 본 연구결과를 이용하여 원전격납구조물의 내부폭발하중 발생 시 손상도 범위 예측이 가능할 것으로 판단된다.