• Title/Summary/Keyword: 면진 원전

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Study on the Performance Improvement of an EQS Device Applied Nuclear Power Plant (원전 EQS 면진장치의 성능개선을 위한 연구)

  • Lee, You In;Lee, Yu Jin;Lee, Hong Pyo;Cho, Myung Sug;Jee, Young Su;Beak, Jun Ho
    • Journal of the Earthquake Engineering Society of Korea
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    • v.19 no.1
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    • pp.13-19
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    • 2015
  • This paper presents the performance improvement of an EQS (Eradic Quake System) device applied to a nuclear power plant. For the nuclear facility, the EQS device needs to be ensured to have high quality, flexibility of design and reliability. To improve the reliability of the design, the hysteresis of the device must be exactly predicted. The friction coefficient of PTFE (PolyTetraFluoroEthylene) and the stiffness of the MER-Spring are considered as the factors influencing the hysteresis curve. In this paper, those factors are analysed to predict the behavior of the device and to improve the equipment of the EQS device. The results of the improved EQS device have been verified via a tests to be comparable with the predicted results. The estimation results indicate that considering those factors is more appropriate than the results of the previous design and method.

Comparison of Seismic Responses of Seismically Isolated NPP Containment Structures using Equivalent Linear- and Nonlinear-Lead-Rubber Bearing Modeling (등가선형 및 비선형 납-고무받침 모델을 이용한 면진된 원전구조물의 지진응답의 비교)

  • Lee, Jin Hi;Song, Jong-Keol
    • Journal of the Earthquake Engineering Society of Korea
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    • v.19 no.1
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    • pp.1-11
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    • 2015
  • In order to perform a soil-isolation-structure interaction analysis of seismically isolated nuclear power plant (NPP) structures, the nonlinear behavior of a seismic isolation system may be converted to an equivalent linear model used in frequency domain analysis. Seismic responses for seismically isolated NPP containment structures subjected to a simple artificial acceleration history and different site class earthquakes are evaluated for the equivalent-linear and nonlinear models that have been applied to lead-rubber bearing (LRB) modeling. It can be observed that the maximum displacements of the equivalent linear model are larger than that of the nonlinear model. From the floor response spectrum analysis for the top of NPP containment structures, it can be observed that the spectral acceleration of an equivalent linear model at about 0.5 Hz frequency is about 2~3 times larger than that of a nonlinear model.

Behavior Analysis of a Seismically Isolated NPP Structure by Varying Seismic Input Generation Method and Strong Ground Motion Duration (입력운동 생성방법과 강진지속시간에 따른 면진원전의 거동 분석)

  • Kim, Hyun-Uk;Joo, Kwang-Ho;Noh, Sang-Hoon;Jung, Chang-Gyun
    • Journal of the Earthquake Engineering Society of Korea
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    • v.17 no.4
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    • pp.187-195
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    • 2013
  • In this paper, firstly, acceleration-time histories were generated by varying strong motion duration in the frequency domain for application to a seismically isolated nuclear power structure, so as to examine the effects of strong motion duration on the behavior of the structure. Secondly, real recorded earthquakes were modified to match the target response spectrum based on the revised SRP 3.7.1(2007) and the modified time histories were applied to the analysis of a seismically isolated nuclear power structure. The obtained values of acceleration and displacement responses of the structure were, finally, compared with the values obtained in case of applying acceleration-time histories generated in the frequency domain to the structure.

Analyses of Vertical Seismic Responses of Seismically Isolated Nuclear Power Plant Structures Supported by Lead Rubber Bearings (납적층고무받침(LRB)으로 지지된 면진 원전 구조물의 수직방향 지진응답 분석)

  • Cho, Sung Gook;Yun, Sung Min;Kim, Dookie;Hoo, Kee Jeung
    • Journal of the Earthquake Engineering Society of Korea
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    • v.19 no.3
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    • pp.133-143
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    • 2015
  • It is very important to assure the seismic performance of equipment as well as building structures in seismic design of nuclear power plant(NPP). Seismically isolated structures may be reviewed mainly on the horizontal seismic responses. Considering the equipment installed in the NPP, the vertical earthquake responses of the structure also should be reviewed. This study has investigated the vertical seismic demand of seismically isolated structure by lead rubber bearings(LRBs). For the numerical evaluation of seismic demand of the base isolated NPP, the Korean standard nuclear power plant (APR1400) is modeled as 4 different models, which are supported by LRBs to have 4 different horizontal target periods. Two real earthquake records and artificially generated input motions have been used as inputs for earthquake analyses. For the study, the vertical floor response spectra(FRS) were generated at the major points of the structure. As a results, the vertical seismic responses of horizontally isolated structure have largely increased due to flexibility of elastomeric isolator. The vertical stiffness of the bearings are more carefully considered in the seismic design of the base-isolated NPPs which have the various equipment inside.

A Probabilistic Study on Seismic Response of Seismically Isolated Nuclear Power Plant Structures using Lead Rubber Bearing (LRB 면진장치를 적용한 원전구조물의 지진응답에 따른 확률론적 연구)

  • Kim, Hyeon-Jeong;Song, Jong-Keol;Moon, Ji-Ho
    • Journal of the Earthquake Engineering Society of Korea
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    • v.22 no.2
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    • pp.45-54
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    • 2018
  • The seismically isolated nuclear power plants shall be designed for design basis earthquake (DBE) and considered to ensure safety against beyond design basis earthquake (BDBE). In order to limit the excessive displacement of the seismic isolation system of the seismically isolated structure, the moat is installed at a certain distance from the upper mat supporting the superstructure. This certain distance is called clearance to stop (CS) and is calculated from the 90th percentile displacement of seismic isolation system subjected to BDBE. For design purposes, the CS can be obtained simply by multiplying the median displacement of the seismic isolation system against DBE by scale factor with a value of 3. The DBE and BDBE used in this study were generated by using 30 sets of artificial earthquakes corresponding to the nuclear standard design spectrum. In addition, latin hyper cube sampling was applied to generate 30 sets of artificial earthquakes corresponding to maximum - minimum spectra. For the DBE, the median displacement and the 99th percentile displacement of the seismic isolation system were calculated. For the BDBE, the suitability of the scale factor was assessed after calculating the 90th percentile displacement of the seismic isolation system.

Soil-Structure Interaction Analysis for Base-Isolated Nuclear Power Plants Using an Iterative Approach (반복법을 이용한 면진적용 원전구조물의 지반-구조물 상호작용 해석)

  • Han, Seung Ryong;Nam, Min Jun;Seo, Choon Gyo;Lee, Sang Hoon
    • Journal of the Earthquake Engineering Society of Korea
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    • v.19 no.1
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    • pp.21-28
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    • 2015
  • The nuclear accident due to the recent earthquake in Japan has triggered awareness of the importance of safety with regard to nuclear power plants (NPPs). An earthquake is one of the most important parameters which governs the safety of NPPs among external events. Application of a base isolation system for NPPs can reduce the risk for earthquakes. At present, a soil-structure interaction (SSI) analysis is essential in the seismic design of NPPs in consideration of the ground structure interaction. In the seismic analysis of the base-isolated NPP, it is restrictive to consider the nonlinear properties of seismic isolation devices due to the linear analysis of the SSI analysis programs, such as SASSI. Thus, in this study, SSI analyses are performed using an iterative approach considering the material nonlinearity of the isolators. By performing the SSI analysis using an iterative approach, the nonlinear properties of isolators can be considered. The difference between the SSI analysis results without iteration and SSI with iteration using SASSI is noticeable. The results of the SSI analysis using an effective linear (non-iterative) approach underestimate the spectral acceleration because the effective linear model cannot consider the nonlinear properties of isolators. The results of the SSI analysis show that the horizontal response of the base-isolated NPP is significantly reduced.

Evaluation of the Soil-structure Interaction Effect on Seismically Isolated Nuclear Power Plant Structures (지반-구조물 상호작용이 면진 원전구조물의 지진응답에 미치는 영향 평가)

  • Lee, Eun-haeng;Kim, Jae-min;Joo, Kwang-ho;Kim, Hyun-uk
    • Journal of the Earthquake Engineering Society of Korea
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    • v.20 no.6
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    • pp.379-389
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    • 2016
  • This study intends to evaluate the conservativeness of the fixed-base analysis as compared to the soil-structure interaction (SSI) analysis for the seismically isolated model of a nuclear power plant in Korea. To that goal, the boundary reaction method (BRM), combining frequency-domain and time-domain analyses in a twofold process, is adopted for the SSI analysis considering the nonlinearity of the seismic base isolation. The program KIESSI-3D is used for computing the reaction forces in the frequency domain and the program MIDAS/Civil is applied for the nonlinear time-domain analysis. The BRM numerical model is verified by comparing the results of the frequency-domain analysis and time-domain analysis for the soil-structure system with an equivalent linear base isolation model. Moreover, the displacement response of the base isolation and the horizontal response at the top of the structure obtained by the nonlinear SSI analysis using BRM are compared with those obtained by the fixed-base analysis. The comparison reveals that the fixed-base analysis provides conservative peak deformation for the base isolation but is not particularly conservative in term of the floor response spectrum of the superstructure.

Evaluation of Seismic Fragility Curve of Seismically Isolated Nuclear Power Plant Structures for Artificial Synthetic Earthquakes Corresponding to Maximum-Minimum Spectrum (최대-최소 스펙트럼에 대응하는 인공합성지진에 대한 면진된 원전구조물의 지진취약도 곡선 평가)

  • Kim, Hyeon-Jeong;Song, Jong-Keol
    • Journal of the Earthquake Engineering Society of Korea
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    • v.23 no.2
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    • pp.89-99
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    • 2019
  • In order to increase the seismic safety of nuclear power plant (NPP) structures, a technique to reduce the seismic load transmitted to the NPP structure by using a seismic isolation device such as a lead-rubber bearing has recently been actively researched. In seismic design of NPP structures, three directional (two horizontal and one vertical directions) artificial synthetic earthquakes (G0 group) corresponding to the standard design spectrum are generally used. In this study, seismic analysis was performed by using three directional artificial synthetic earthquakes (M0 group) corresponding to the maximum-minimum spectrum reflecting uncertainty of incident direction of earthquake load. The design basis earthquake (DBE) and the beyond design basis earthquakes (BDBEs are equal to 150%, 167%, and 200% DBE) of G0 and M0 earthquake groups were respectively generated for 30 sets and used for the seismic analysis. The purpose of this study is to compare seismic responses and seismic fragility curves of seismically isolated NPP structures subjected to DBE and BDBE. From the seismic fragility curves, the probability of failure of the seismic isolation system when the peak ground acceleration (PGA) is 0.5 g is about 5% for the M0 earthquake group and about 3% for the G0 earthquake group.

Effects of Significant Duration of Ground Motions on Seismic Responses of Base-Isolated Nuclear Power Plants (지진의 지속시간이 면진원전의 지진거동에 미치는 영향)

  • Nguyen, Duy-Duan;Thusa, Bidhek;Lee, Tae-Hyung
    • Journal of the Earthquake Engineering Society of Korea
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    • v.23 no.3
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    • pp.149-157
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    • 2019
  • The purpose of this study is to investigate the effects of the significant duration of ground motions on responses of base-isolated nuclear power plants (NPPs). Two sets of ground motion records with short duration (SD) and long duration (LD) motions, scaled to match the target response spectrum, are used to perform time-history analyses. The reactor containment building in the Advanced Power Reactor 1400 (APR1400) NPP is numerically modeled using lumped-mass stick elements in SAP2000. Seismic responses of the base-isolated NPP are monitored in forms of lateral displacements, shear forces, floor response spectra of the containment building, and hysteretic energy of the lead rubber bearing (LRB). Fragility curves for different limit states, which are defined based on the shear deformation of the base isolator, are developed. The numerical results reveal that the average seismic responses of base-isolated NPP under SD and LD motion sets were shown to be mostly identical. For PGA larger than 0.4g, the mean deformation of LRB for LD motions was bigger than that for SD ones due to a higher hysteretic energy of LRB produced in LD shakings. Under LD motions, median parameters of fragility functions for three limit states were reduced by 12% to 15% compared to that due to SD motions. This clearly indicates that it is important to select ground motions with both SD and LD proportionally in the seismic evaluation of NPP structures.