• 대한기계학회논문집 C: 기술과 교육
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• 제3권3호
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• pp.193-199
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• 2015

슬로싱 하중은 LNG 화물창의 내부 구조물에 강한 충격을 유발시킨다. 이는 슬로싱 하중에 의해 평면이나 구석 부위에 순간 압력을 증가시키기 때문에 멤브레인 타입의 화물창에서는 매우 위험하다. 멤브레인 타입의 화물창은 선체구조에 비해 매우 유연하므로, 유체-구조 상호작용은 슬로싱 하중을 받는 화물창의 구조해석에서 매우 중요한 역할을 한다. 본 연구는 유한요소해석 기법을 이용하여 LNG 유체와 KC-1 단열시스템의 경계에 대시포트를 이용하여 유체-구조 상호작용을 고려한 해석 방법에 대해 다루었다. 결론적으로 표면 완충 효과를 적용하였을 경우, KC-1 단열시스템의 폴리우레탄폼에서 발생하는 최대응력이 약 1.5 배 낮아지는 효과가 있음을 알아내었다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2007년도 추계학술대회논문집
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• pp.1197-1202
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• 2007

The paper deals with the structural analysis and vibration test for the scaffolding system of LNG cargo containment. The eight-stories scaffolding system has telescopic area, working area, coner area and storage area in real system. In the structural analysis, the maximum displacement and stress of the each floor for the scaffolding system are investigated by finite element method. In the vibrational analysis, the natural frequencies and mode shapes for 8-stories scaffolding system of the LNG cargo containment are investigated. In order to compare theoretical natural frequencies with experimental ones, small size of 2-step scaffolding structure is used, and the theoretical results for natural frequency have a good agreement with experimental ones.

• 한국소음진동공학회논문집
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• 제20권6호
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• pp.546-554
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• 2010

The paper deals with the structural analysis and vibration test for the scaffolding system of LNG cargo containment. The eight-stories scaffolding system has telescopic area, working area, coner area and storage area in real system. In the structural analysis, the maximum displacement and stress of the each floor for the scaffolding system are investigated by finite element method. In the vibrational analysis, the natural frequencies and mode shapes for 8-stories scaffolding system of the LNG cargo containment are investigated. In order to compare theoretical natural frequencies with experimental ones, small size of 2-step scaffolding structure is used, and the theoretical results for natural frequency have a good agreement with experimental ones.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.241-253
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• 2001

Under severe accidents, the pressure and temperature response has an important role for the integrity of a nuclear power plant containment. The history of the pressure and temperature is characterized by the amount and state of steam/air mixture in a containment. Recently, the heat transfer rate to the structure surface is supposed to be increased by the wavy interface formed on condensate film. However, in the calculation by using CONTAIN code, the condensation heat transfer on a containment wall is calculated by assuming the smooth interface and has a tendency to be underestimated for safety. In order to obtain the best- estimate heat transfer calculation, we investigated the condensation heat transfer model in CONTAIN 1.2 code and adopted the new forced convection correlation which is considering wavy interface. By using the film tracking model in CONTAIN 1.2 code, the condensate film is treated to consider the effect of wavy interface. And also, it was carried out to investigate the effect of the different cell modelings - 5-cell and 10-cell modeling - for KNGR(Korean Next Generation Reactor) containment phenomena during a severe accident. The effect of wavy interface on condensate film appears to cause the decrease of peak temperature and pressure response . In order to obtain more adequate results, the proper cell modeling was required to consider the proper flow of steam/air mixture.

• 콘크리트학회논문집
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• 제22권6호
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• pp.817-824
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• 2010

약 콘크리트 격납구조물은 구조적 안전성이 뛰어나고 경제적이므로 원자력발전소 격납건물, LNG 저장탱크 등에 널리 사용되고 있다. 격납구조물 중 지붕 돔의 형태는 구조적 안전성, 물량 및 시공 난이도에 큰 영향을 미치므로 최적의 두께와 곡률을 도출하고자 하는 노력이 필요하다. 한편 일반적으로 PSC 구조로 설계되는 링빔은 이러한 돔을 지지하여 벽체의 변형을 최소화시키는 역할을 하며, 단면 크기와 더불어 프리스트레스 수준을 적절히 결정하는 것이 설계의 핵심이 된다. 이 연구에서는 축대칭 회전쉘의 막이론을 적용하여 본설계 시의 유한요소해석에 앞서 돔과 링빔의 초기 형상이나 프리스트레스 수준을 효율적으로 결정할 수 있는 기법을 제안하였다. 이러한 기법을 국내에서 시공된 격납구조물의 돔과 링빔에 적용하여 분석하고 단면 형상이나 프리스트레싱 설계에 대한 개선 방안을 고찰하였다.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2696-2707
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• 2021

The purpose of this study is to investigate the efficiency of various structural modeling schemes for evaluating seismic performances and fragility of the reactor containment building (RCB) structure in the advanced power reactor 1400 (APR1400) nuclear power plant (NPP). Four structural modeling schemes, i.e. lumped-mass stick model (LMSM), solid-based finite element model (Solid FEM), multi-layer shell model (MLSM), and beam-truss model (BTM), are developed to simulate the seismic behaviors of the containment structure. A full three-dimensional finite element model (full 3D FEM) is additionally constructed to verify the previous numerical models. A set of input ground motions with response spectra matching to the US NRC 1.60 design spectrum is generated to perform linear and nonlinear time-history analyses. Floor response spectra (FRS) and floor displacements are obtained at the different elevations of the structure since they are critical outputs for evaluating the seismic vulnerability of RCB and secondary components. The results show that the difference in seismic responses between linear and nonlinear analyses gets larger as an earthquake intensity increases. It is observed that the linear analysis underestimates floor displacements while it overestimates floor accelerations. Moreover, a systematic assessment of the capability and efficiency of each structural model is presented thoroughly. MLSM can be an alternative approach to a full 3D FEM, which is complicated in modeling and extremely time-consuming in dynamic analyses. Specifically, BTM is recommended as the optimal model for evaluating the nonlinear seismic performance of NPP structures. Thereafter, linear and nonlinear BTM are employed in a series of time-history analyses to develop fragility curves of RCB for different damage states. It is shown that the linear analysis underestimates the probability of damage of RCB at a given earthquake intensity when compared to the nonlinear analysis. The nonlinear analysis approach is highly suggested for assessing the vulnerability of NPP structures.

• 한국전산유체공학회지
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• 제10권3호
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• pp.9-18
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• 2005

During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In order to mitigate hydrogen hazards possibly occurred in the NPP containment, hydrogen mitigation system (HMS) is usually adopted. The design of the next generation NPP (APR1400) designed in Korea specifies 26 passive autocatalytic recombiners and 10 igniters installed in the containment for the hydrogen mitigation. in this study, the analysis of the hydrogen and steam behavior during a total lose of feed water (TLOFW) accident in the APR1400 containment has been conducted by using the CFD code GASFLOW. During the accident, a huge amount of hot water, steam, and hydrogen is released in the in-containment refueling water storage tank (IRWST). The current design of the APR1400 includes flap-type dampers at the IRWST vents which are operated depending on the pressure difference between inside and outside of the IRWST. it was found that the flaps strongly affects the flow structure of the steam and hydrogen in the containment. The possibilities of a flame acceleration and transition from deflagration to detonation (DDT) were evaluated by using Sigma-Lambda criteria. Numerical results indicate the DDT possibility could be heavily reduced in the IRWST compartment when the flaps are installed.

• 한국지진공학회논문집
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• 제17권2호
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• pp.53-59
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• 2013

Several researches have been studied to enhance the seismic performance of nuclear power plants (NPPs) by application of seismic isolation. If a seismic base isolation system is applied to NPPs, seismic performance of nuclear power plants should be reevaluated considering the soil-structure interaction effect. The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP structures and equipment. In this study, the seismic performance of an isolated NPP is evaluated by seismic fragility curves considering the soil-structure interaction effect. The designed seismic isolation is introduced to a containment building of Shin-Kori NPP which is KSNP (Korean Standard Nuclear Power Plant), to improve its seismic performance. The seismic analysis is performed considering the soil-structure interaction effect by using the linearized model of seismic isolation with SASSI (System for Analysis of Soil-Structure Interaction) program. Finally, the seismic fragility is evaluated based on soil-isolation-structure interaction analysis results.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.370.1-370
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• 1999

• 대한토목학회논문집
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• 제31권5A호
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• pp.369-378
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• 2011

본 논문은 RC(Reinforced Concrete), SC(Steel-Plate Concrete) 격납구조에 대한 대형 민항기 충돌에 관한 응답해석을 Hydrocode인 Autodyn-3D를 통해 수행하였다. 이전에 연구된 대부분의 항공기 충돌 해석에서의 충격 하중은 국부적인 부분(동체면적의 약 2배)에 대해 Riera의 충격하중함수를 적용하는 방법을 이용하여왔다. 하지만, 본 논문에서는 실제 Boeing 767과 유사한 모델을 구현하여 대상 구조체에 직접 충돌 시켜 나타나는 현상을 비교 분석 하였으며, 항공기 모델은 강성벽(Rigid Target)에 대해 항공기를 충돌 시켰을 시 발생되는 충돌하중이력곡선과, Riera 함수를 이용한 충돌하중이력곡선과의 비교를 통하여 검증하였다. 항공기 충돌 시, SC 격납구조에 대한 충돌저항능력 및 응답, 안전성 효과를 평가 하기 위해 무근 콘크리트(Plain Concrete:PC), 철근 콘크리트(Reinforced Concrete:RC), 철근 콘크리트와 완전 부착된 내부 Liner Plate(CLP:Containment Liner Plate), 그리고 SC 격납구조에 대한 해석을 수행하였다. 따라서 항공기 충돌과 같은 비정상충격하중이 RC구조와 SC구조에 가해질 경우에 대한 거동 예측이 가능하며, 보수적인 안전성이 요구되는 RC 원전 격납건물에 SC구조를 적용하면 상대적인 안전성 증대 효과를 기대 할 수 있을 것으로 보여진다.