Effect of slab stiffness on floor response spectrum and fragility of equipment in nuclear power plant building
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The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the floor slab as a rigid diaphragm. In the present study, to study the variation of seismic response in a floor, the FRSs at different locations were generated by 3-D finite element model, and the response was compared to that of the rigid diaphragm model. The result showed that the FRS significantly varied due to the large opening in a floor, which was not captured by the rigid diaphragm model. Based on the result, seismic fragility analysis was performed for the anchorage of a heat exchanger, to investigate the effect of location-dependent FRS disparity on the high confidence low probability of failure (HCLPF).
Abstract
The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the floor slab as a rigid diaphragm. In the present study, to study the variation of seismic response in a floor, the FRSs at different locations were generated by 3-D finite element model, and the response was compared to that of the rigid diaphragm model. The result showed that the FRS significantly varied due to the large opening in a floor, which was not captured by the rigid diaphragm model. Based on the result, seismic fragility analysis was performed for the anchorage of a heat exchanger, to investigate the effect of location-dependent FRS disparity on the high confidence low probability of failure (HCLPF).
참고문헌 (34)
- 이은행, "Evaluation of the Soil-structure Interaction Effect on Seismically Isolated Nuclear Power Plant Structures", 한국지진공학회논문집, 20(6), pp.379~389 (2016), 한국지진공학회
- V. Varma, "Simplified approach for seismic analysis of structures", Int. J. Struct. Stabil. Dynam, 2(2), pp.207~225 (2002)
- Y. -N. Huang, "Seismic performance assessment of baseisolated safety-related nuclear strucures", Earthq. Eng. Struct. Dynam, 39(13), pp.1421~1442 (2010)
- Duy-Duan Nguyen, "Identifying signifi cant earthquake intensity measures for evaluating seismic damage and fragility of nuclear power plant structures", Nuclear Engineering and Technology, 52(1), pp.192~205 (2020), 한국원자력학회
- J.R. Nie, "A study of the effect of floor flexibility on building response using the KK NPP experience", Transactions of the 22nd International Conference on the Structural Mechanics in Reactor Technology (2013)
- B.B. Torkian, "Validation of lumped mass stick models for surface founded structures", Transactions of the 22nd International Conference on the Structural Mechanics in Reactor Technology (2013)
- G. Hardy, "Finite element and lumped mass structure modelling for SPRAs", Transactions of the 23rd International Conference on the Structural Mechanics in Reactor Technology (2015)
- T. Radford, "A case study on the effect of detailed 3D finite element modelling on nuclear power plant building response", Transactions of the 23rd International Conference on the Structural Mechanics in Reactor Technology (2015)
- S. El-Bahey, "Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary control building", Transactions of the 24th International Conference on the Structural Mechanics in Reactor Technology (2017)
- S. Damolini, "Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary", control building, 2019, ~
- 최인길, "설계초과 지진에 대한 원전 지진안전성 평가기술 고찰 및 제언", 한국압력기기공학회 논문집, 13(1), pp.1~15 (2017), 한국압력기기공학회[DOI]
- Development of Criteria for Seismic Review of Selected Nuclear Power Plants, "U.S. NRC", U.S. Nuclear Regulatory Commission, ~, pp.DC NUREG (1978), CR-0098
- Seismic Analysis of Safety-Related Nuclear Structures, "ASCE", American Society of Civil Engineers, ~, pp.ASCE (2017), SEI 4-16
- Technical Basis for Revision of Regulatory Guidance on Design Grond Motions: Hazard-and Risk-Consistent Ground Motion Spectra Guidelines, "U.S. NRC", U.S. Nuclear Regulatory Commission, ~, pp.NUREG (2001), CR-6728
- Selecting and Scaling Earthquake Ground Motions for Performing Response-History Analyses, "NIST", National Institute of Standards and Technology, ~, pp.NIST GCR 11-917-15 (2011)
- Standard Review Plan, Revision 4, "U.S. NRC", Nuclear Regulatory Commission, ~, pp.NUREG-0800 (2014)
- Technical Manual for Strata, "A.R. Kottke", Pacific Earthquake Engineering Research Center, University of California, ~, pp.Report No.2008 (2008), 10
- Probabilistic Models of Site Velocity Profiles for Generic and Sitespecific Ground-Motion Amplification Studies, "G. R. Toro", Brookhaven National Laboratory, ~ (1995)
- M. B. Darendeli, "Development of a New Family of Normalized Modulus Reduction and Material Damping Curves", pp.2001
- ANSYS, Inc., "Ansys® Mechanical, Release 20.2", ~ (2020)
- ACI Committee 318, Building Code Requirements for Structural Concrete, , American Concrete Institute, 318~319 (2019)
- Damping Values for Seismic Design of Nuclear Power Plants, Revision 1, "U.S. NRC", U.S. Nuclear Regulatory Commission, ~, pp.RG 1.61 (2007)
- Finite Element Seismic Models for SSI Analyses of the NI Buildings of the APR1400 Standard Plant, "KEPCO", Korea Electric Power Corporation &Korea Hydro & Nuclear Power Co., Ltd, ~, pp.ML13304A931 (2013)
- Seismic Fragility and Seismic Margin Guidance for Seismic Probabilistic Risk Assessments, "EPRI", Electric Power Research Institute, ~, pp.EPRI-3002012994 (2018)
- R. P. Kennedy, "Probabilistic seismic safety study of an existing nuclear power plant", Nucl. Eng. Des, 59(2), pp.315~338 (1980)
- MATLAB, "9.11.0.1809720 (R2021b)", The MathW orks Inc, ~ (2018)
- Seismic Design Bases for the APR1400 Standard Plant Design, "KEPCO", Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd., ~, pp.APR1400-E-S-NR-13001-NP (2013)
- Status Report - APR1400 (KEPCO E&C, "KHNP)", KEPCO, 2020
- 김민규, "원전 전기캐비넷의 지진취약도 재평가를 위한 진동대 실험", 한국전산구조공학회논문집, 24(3), pp.295~306 (2011), 한국전산구조공학회
- G. K. Kulak, "Guide to Design Criteria for Bolted and Riveted Joints" (1987), Wiley & Son
- ACI Committee 349, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary, , American Concrete Institute, ~, pp.ACI 349-13 (2013)
- R. Eligehausen, "Behavior of fasteners loaded in tension in cracked reinforced concrete", Structural Journal, 92(3), pp.365~379 (1995)
- R. Eligehausen, "Anchorage in Concrete Construction" (2006), Ernst &Sohn
- H.H.M. Hwang, "Determination of HCLPF value for seismic margins study", Transactions of the 10th SMiRT (1989)