• 한국지진공학회:학술대회논문집
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• 한국지진공학회 1999년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall
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• pp.37-44
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• 1999

Spectral characteristic of Kyeongju earthquake occurred on the June 2, 1999 with magnitude 3,4 is analyzed. It is guessed that the stress energy release of source within relatively short period caused the ground near the epicenter to vibrate with large amplitude for the magnitude and predominantly high frequency. The cumulative absolute velocity and average spectrum acceleration are 0.034 gsec and 0.118g, respectively lower than threshold values of potential earthquake damage which is consistent with the investigation of damage in field. The analysis of the acceleration records of Kyeongju earthquake shows the need to develop the ration criterion for the determining the operating basis earthquake of nuclear power plant.

• 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.

• Structural Engineering and Mechanics
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• 제2권2호
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• pp.157-171
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• 1994

A general approach to the dynamic time-history analysis of the reactor core is presented in this paper as a part of the fuel assembly qualification program. Several detailed core models are set up to reflect the placement of the fuel assemblies within the core shroud. Peak horizontal responses are obtained for each model for the motions induced form earthquake. The dynamic responses such as fuel assembly deflected shapes and spacer grid impact loads are carefully investigated. Also, the sensitivity responses are obtained for the earthquake motions and the fuel assembly non-linear response characteristics are discussed.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2006년도 학술발표회 논문집
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• pp.56-63
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• 2006

Facilities of 76skV Substation(S/S) play an important role in electric power supply grids. Various power facilities of 765kV S/S might be damaged enormously if a strong earthquake occurs. In an effort to mitigate possible earthquake disasters, KEPRI (Korea Electric Power Research Institute) set forth plans to verify seismic safety of the facilities of 765kV S/S. To accomplish the task, an earthquake monitoring systems is constructed at four 765kV S/S sites(Shin-AnSung, Shin-TaeBaek, Shin-SeoSan and Shin-GaPyung). Data from these earthquake monitoring stations are being transmitted via satellite communication. Currently, KEPRI is operating an earthquake monitoring system in freefield of Shin-SeoSan S/S (NSS) tentatively, Also, the data from NSS is preliminarily analyzed using the horizontal to vertical (H/V) spectrum ratio method. The method of H/V spectrum ratio has been used to infer site amplification without previous knowledge of near surface geology. The results of data analysis shorts good S/N ratio and amplification of 20-25 Hz by site effect. In the near future, the accumulated data is expected to provide a basis for assessing and predicting any damages to integrity of 765kV S/S facilities by earthquakes.

• 소음진동
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• 제7권1호
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• pp.33-41
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• 1997

경수로형 원자력발전소 표준화 작업의 일환으로 만들어진 한국표준형 원자력 발전소는 그 건설부지를 한반도뿐만 아니라 인접 아시아국가의 여러곳을 목표로 하고 있으며 이와 관련하여 안전정지지진의 레벨을 0.3g로 증가시키려는 시도가 계획되고 있다. 본 연구에서는 이와 같은 지진레벨 증가가 기존의 0.2g로 설계된 원자로 내부 구조물과 핵연료집합체에 미치는 영향을 평가하였다. 운전기준지진 및 안전정지지진의 응답을 비교함으로써 비선형 응답특성을 조사하였고 한국표준형 원자력발전소의 원자로 내부구조물 및 핵연료집합체의 설계 타당성에 대하여 언급하였다.

• 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.

• 전산구조공학
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• 제4권4호
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• pp.24-28
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• 1991

본 연구용역에서는 반도기계주식회사의 의뢰에 의거하여 Manbridge Crane의 지진하중에 대한 구조물의 안전성을 평가하였다. 구조해석은 유한요소 모형을 사용하여 사하중, 활하중 및 OBE(Operating Basis Earthquake)와 SSE(Safe Shut-down Earthquake)의 지진하중에 관한 해석을 수행하였다. Crane설치지점의 층응답스펙트럼을 입력으로 한 응답스펙트럼해법으로 지진해석을 수행하였다. Trolley의 위치와 정격하중의 유무에 따라서 5개의 구조모형을 작성하여 해석을 수행하였으며, 지진해석에는 35개의 자유진동모드가 고려되었다. 구조해석을 통하여 1) 구조부재의 과도응력 발생여부, 2) 보강재의 좌굴 가능성, 3) Hoist Rope의 안전성, 4) Crane의 전도의 가능성 및 Seismic Lug의 안전성, 5) 지진하중에 대한 제동력, 6) Crane의 주행 Rail로부터의 탈선여부, 7) Traversing Rail의 수직처짐, 8) 주행 Rail 및 End Stopper의 Anchor Bolt의 안정성, 9) Fuel Basket과 Handrail의 안전성을 검토하였다. 해석결과를 바탕으로 설계시방서에서 제시한 모든 설계요구조건을 만족시킬 수 있도록 수직 Frame의 보강부재를 보강하고, Hoist Rope 용량을 증가시키도록 제안하였다.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2038-2045
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• 2021

The main objective of this work is to propose a reliable routine standard operation procedures (SOP) for structural health monitoring and diagnosis of nuclear power plants (NPPs). At present, NPPs have monitoring systems that can be used to obtain the quantitative health record of containment (CTMT) buildings through system identification technology. However, because the measurement signals are often interfered with by noise, the identification results may introduce erroneous conclusions if the measured data is directly adopted. Therefore, this paper recommends the SOP for signal screening and the required identification procedures to identify the dynamic characteristics of the CTMT of NPPs. In the SOP, three recommend methods are proposed including the Recursive Least Squares (RLS), the Observer Kalman Filter Identification/Eigensystem Realization Algorithm (OKID/ERA), and the Frequency Response Function (FRF). The identification results can be verified by comparing the results of different methods. Finally, a preliminary CTMT healthy record can be established based on the limited number of earthquake records. It can be served as the quantitative reference to expedite the restart procedure. If the fundamental frequency of the CTMT drops significantly after the Operating Basis Earthquake and Safe Shutdown Earthquake (OBE/SSE), it means that the restart actions suggested by the regulatory guide should be taken in place immediately.