• 한국전산구조공학회논문집
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• 제24권3호
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• pp.289-294
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• 2011

본 논문에서는 유한요소모델을 사용하여 원자력 발전용 해수여과장치에 대한 동적 내진해석을 수행하였다. 장치의 검증을 위해서 운전기준지진(Operating Basis Earthquake, OBE)과 안전정지지진(Safe Shutdown Earthquake, SSE)이 설계하중으로 작용하였을 때 부재에 미치는 영향을 평가하였다. 해석대상은 유한요소법을 사용하여 수학적 모델링을 완성하였고, 층응답스펙트럼(Floor Response Spectrum, FRS)에 따른 지진하중과 사하중 등을 적용하여 해석을 수행하였다. 해석된 해수여과장치의 최대변위는 OBE 조건에서 2.5mm이고, SSE 조건에서 최대변위는 4.6mm이다. 최대응력은 OBE 조건에서 24MPa, SSE 조건에서 44MPa이며, 이 값은 재료의 항복강도의 각각 18%, 27% 수준이다. 이에 따라 지진하중 조건에 따른 해수여과장치의 구조적 안전성이 제시되었다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2011년도 추계학술대회 논문집
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• pp.480-485
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• 2011

In this study, the seismic analysis of power plant piping system was performed using finite element model. This study was performed by ANSYS 12.1. For qualification of power plant piping system, the response spectrum analysis was performed using the given operating basis earthquake(OBE) and safe shutdown earthquake(SSE) floor response spectrum. The maximum stresses of power plant piping system were 166 MPa under OBE condition and 281 MPa under SSE condition. Thus, it can shown that the structural integrity of tpower plant piping system has a stable structure for seismic load conditions.

• 대한기계학회논문집A
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• 제35권10호
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• pp.1265-1271
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• 2011

본 논문에서는 유한요소 모델을 사용한 유체-구조 해석을 통하여 원자력 발전소 임시 받침대의 내진에 대한 안전성을 평가하였다. 임시받침대는 수중에 존재하기 때문에 유체-구조 연성을 통하여 유체의 영향을 고려하였다. 유체의 영향은 구조물의 단위길이당 추가질량으로 정의하여 적용하였다. 각각의 운전기준지진(OBE)과 안전정지지진(SSE)의 설계조건을 층응답스펙트럼(Floor Response Spectrum: FRS)으로 적용하여 진동해석과 내진해석을 수행하였다. 해석된 임시받침대의 최대변위는 운전기준지진에서 0.29mm 이고, 운전정지지진에서 최대변위는 0.36 mm 이다. 최대응력은 운전 기준지진에서 17.9 MPa, 안전정지지진에서 19.6 MPa 이며, 이 값은 재료의 항복강도의 23 %, 14 % 수준이다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2002년도 춘계학술대회논문집
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• pp.1210-1215
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• 2002

The spent fuel handling tool is used to handle the refuel bundle and treated by hoist rope on the bridge crane. The new developed handling tool of NPP(Nuclear Power Plant) should be conformed the structural stability under earthquake condition. In this study, the stress and seismic analysis of the handling tool are performed by finite element method. Using the Floor Response Spectrum(FRS) obtained through the time history analysis, the modal and seismic analysis under Operating Basis Earthquake(OBE) and Safe Shutdown Earthquake(SSE) load conditions are carried out. Total 4 cases of different locations of the trolly and the hook are investigated. With the spring-damper element, the tension analysis of hoist rope is conducted. The stability of handling tool under earthquake load condition is conformed with regulatory guide.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 추계학술대회논문집A
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• pp.465-470
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• 2001

In this study, the seismic analysis of rack structure with fluid-structure interaction is performed through use of the Finite Element Method(FEM) code ANSYS. Fluid-structure interaction can specify in terms of an hydrodynamic effect which is defined as the added mass per unit length divided by the area of the cross section. Using the Floor Response Spectrum(FRS) obtained through the time-history analysis, modal analysis and seismic analysis under Operating Basis Earthquake(OBE) and Safe Shutdown Earthquake(SSE) condition is carried out. The fluid-structure interaction effects on the rack structure are investigated.

• 한국소음진동공학회논문집
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• 제22권7호
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• pp.599-604
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• 2012

In this study, the safety of the driving gear reducer of ESW(essential service water) traveling sea water screen was evaluated through seismic analysis. Mode analysis of gear reducer was performed for reliability of analysis. Seismic analysis was performed in operating basis earthquake(OBE) and safe shutdown earthquake(SSE), which were applied as design condition using floor response spectrum( FRS). The maximum strain of gear reducer under OBE and SSE were 20.4 ${\mu}$ and 33.6 ${\mu}$, respectively. The maximum stresses were 2.42 MPa under OBE condition and 4.36 MPa under SSE condition, which were smaller than the allowable strength of material.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2011년도 추계학술대회 논문집
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• pp.731-736
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• 2011

In this study, the safety of the driving gear reducer of ESW traveling sea water screen was evaluated through seismic analysis. Mode analysis of gear reducer was performed for reliability of analysis. Seismic analysis was performed in Operating Basis Earthquake(OBE) and Safe Shutdown Earthquake(SSE), which was applied as design condition using Floor Respnse Spectrum(FRS). The maxsimum displacement of gear reducer under OBE and SSE were 0.0137 mm and 0.0241 mm, respectively. The maximum stress of gear reducer under OBE and SSE were 2.42 MPa and 4.36 MPa, respectively.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2011년도 정기 학술대회
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• pp.462-465
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• 2011

본 논문에서는 유한요소모델을 사용하여 원자력 발전용 해수 여과장치에 대한 동적 내진해석을 수행하였다. 장치의 검증을 위해서 운전기준지진(Operating Basis Earthquake, OBE)과 안전정지지진(Safe Shutdown Earthquake, SSE)이 설계하중으로 작용하였을 때 부재에 미치는 영향을 평가하였다. 해석대상은 유한요소법을 사용하여 수학적 모델링을 완성하였고, 층응답스펙트럼(Floor Response Spectrum, FRS)에 따른 지진하중과 사하중등을 적용하여 해석을 수행하였다. 해석된 해수여과장치의 최대변위는 OBE 조건에서 2.5 mm 이고, SSE 조건에서 최대변위는 4.6 mm 이다. 최대응력은 OBE 조건에서 24 MPa, SSE 조건에서 44 MPa이며, 이 값은 재료의 항복강도의 각각 18%, 27% 수준이다. 이에 따라 지진하중조건에 따른 해수여과장치의 구조적 안전성이 제시되었다.

• Earthquakes and Structures
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• 제8권3호
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• pp.779-799
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• 2015

The slosh height and the possibility of water spill from rectangular Spent Fuel Storage Bays (SFSB) and Tray Loading Bays (TLB) of Nuclear power plant (NPP) are studied during 0.2 g, Safe Shutdown Earthquake (SSE) level of earthquake. The slosh height obtained through Computational Fluid dynamics (CFD) is compared the values given by TID-7024 (Housner 1963) and American concrete institute (ACI) seismic codes. An equivalent amplitude method is used to compute the slosh height through CFD. Numerically computed slosh height for first mode of vibration is found to be in agreement the codal values. The combined effect in longitudinal and lateral directions are studied separately, and found that the slosh height is increased by 24.3% and 38.9% along length and width directions respectively. There is no liquid spillage under SSE level of earthquake data in SFSB and TLB at convective level and at free surface acceleration data. Since seismic design codes do not have guidelines for combined excitations and effect of higher modes for irregular geometries, this CFD procedure can be opted for any geometries to study effect of higher modes and combined three directional excitations.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2001년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall 2001
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• pp.67-74
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• 2001

This paper presents the Safe Shutdown Earthquake(SSE) input motion for the seismic design of the Advanced Power Reactor 1400(APR1400). The Design Ground Response Spectra(DGRS) far the SSE is based on the design spectrum specified in regulatory Guide(RG) 1.60 of U.S. Nuclear Regulatory Commission(US NRC), anchored to a Peak Ground Acceleration(PGA) of 0.3g and enriched in the high frequency range. This SSE seismic input motion is to be applied to the seismic analysis as the free-field seismic motion at the ground surface of both the rock and generic soil sites fur APRI1400. The enrichment for APR1400 seismic input motion is performed considering the current US NRC regulations, the seismic hazard studies performed by the Lawrence Livermore National Laboratory (LINL) and Electric Power Research Institute(EPRI) for the Central and Eastern United States nuclear power plant sites, and the seismic input motions used in the design certifications of the three existing U.S. advanced standard plants. It is represented by a set of DGRS and the accompanying Target Power Spectral Density(PSD) Function in both the horizontal and vertical directions.